Xains Info: June 2008

INFO KILAT: 2 Langkah Melindungi 'Data Rahasia' di Situs Web

Tips & Tricks 2 Langkah Melindungi 'Data Rahasia' di Situs Web Penulis: Ahmad Suwandi - detikinet Jakarta - Dalam sebuah hosting atau web server, seringkali ditemui banyak folder-folder. Kebanyakan berupa folder penyimpanan Content Management System (CMS) atau aplikasi dan plugins. Namun, adakalanya juga seorang user menyimpan data dalam folder di web server atau hosting. Tujuannya, untuk berbagi file dengan orang lain. Misalnya, Anda meletakkan dalam folder Data_Rahasia. Kemudian link atau URL lokasinya dibagi ke orang lain agar bisa diunduh. Alamatnya adalah www.webanda.com/Data_Rahasia/. Fenomena yang (sayangnya) kerap dilakukan di situs `pelat merah` ini sebenarnya sangat beresiko. Bisa jadi, dengan bantuan mesin pencari, data yang kita simpan diambil oleh orang yang tidak diharapkan. Untuk mencegah hal itu, ada sebuah cara yang bisa digunakan. Hanya dengan membuat sebuah file sederhana. Sebuah file yang lazim dikenal dengan nama .htaccess. Dengan file .htaccess, maka file dalam folder penyimpanan tidak bisa dibuka melalui browser. Hanya bisa dibuka menggunakan aplikasi File Transfer Protocol (FTP) atau melalui fitur File Manager dalam control panel hosting. Berikut ini langkah-langkahnya: Pertama, membuat file .htaccess. * Bukalah aplikasi editor teks yang biasa Anda pakai. * Pengguna Windows bisa menggunakan Notepad, pengguna Linux bisa menggunakan Text Editor atau perintah vi dalam console mode. Sedangkan pengguna Mac bisa menggunakan TextEdit. * Isikan baris-baris perintah ini: AuthType Basic AuthName “Test .htaccess” Require user test * Simpan file ini dengan nama .htaccess. Jika tidak diizinkan oleh sistem operasi Anda menyimpan file bernama .htaccess, simpan saja dalam nama yang lain. Kedua, upload file .htaccess dalam folder yang ingin Anda lindungi. * Dalam hal ini di www.webanda.com/Data_Rahasia/. * Upload biasanya dilakukan menggunakan FTP. * Setelah selesai, ubah nama file menjadi .htaccess. Voila! Folder Anda www.webanda.com/Data_Rahasia/) sudah tidak bisa diakses sekarang. sumber : www.detikinet.com/ppin www.detikinet.com/ppin : 2008

Improvement in oil seal performance of gas compressor in HTTR

Oyama,-Sunao (Mitsubishi Heavy Industries, Ltd., Tokyo (Japan)); Hamamoto,-Shimpei; Nemoto,-Takahiro; Sekita,-Kenji; Isozaki,-Minoru; Emori,-Kouichi; Ohta,-Yukimaru; Mizushima,-Toshihiko (Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan)); Kaneshiro,-Noriyuki; Ito,-Yoshiteru; Yamamoto,-Hideo (Kaji Technology Corp., Sakai, Osaka (Japan) High-Temperature engineering Test Reactor (HTTR) built by Japan Atomic Energy Agency (JAEA) has reciprocating compressor commonly used to extract and discharge helium gas into primary/secondary coolant helium loop from helium purification system. Piston rod seal of the compressor consist of several components to prevent coolant leak. However, rod seal system has weak reliability during long term operation due to repeated leakage of seal oil in operation. As a result of investigations, leakage's root is found in that seal were used in a range beyond limit sliding properties of seal material. For this reason, a lip of the seal was worn and transformed itself and was not able to sustain a seal function. Therefore, through tests using facility actual equipment for endurance of candidate materials, one seal material were chosen for long term operation.

CANDU construction and operating experience in Canada.

There have been a dozen or so different reactor systems developed to the prototype stage, and the CANDU reactor in Canada is one of only three or four types that have been firmly established as a competitive source of electric energy. The success of Canada with CANDU resulted from the efforts of all concerned over the past 30 years. The most powerful stimulus to the development of CANDU was the virtual exhaustion of economic hydroelectric resources in Ontario, and the recognition that the increasing dependence on foreign fossil energy sources is undesirable. Beginning with a small demonstration plant of 20 MW, then a prototype CANDU station of 200 MW, Ontario Hydro, with AECL, developed an engineering capability and produced the first commercial, multi-unit CANDU design for Pickering NGS. Hydrofurther developed and refined its project management techniques to meet the challenge presented by the nuclear power mega-projects. Quebec and New Brunswick have also entered the nuclear power field by choosing a single unit 600 MW CANDU station, instead of the multi-unit approach. The operating experience of CANDU is entirely in Ontario, and the record has shown the solid success. CANDU is a highly salable product in the international market. (Kako, I.). Campbell,-P.G. (Ontario Hydro, Toronto (Canada)); Amyot,-P.; O'Connor,-A.J.

Irradiation experiments of Fugen PuO sup 2 -UO sup 2 fuel assembly in WSGHWR.

Four irradiation tests, type A, B, C and D, have been carried out for the development of the design and fabrication of fuel assembly for the advanced thermal reactor ''Fugen''. This paper reports on the irradiation conditions and the results of post-irradiation tests for the type D fuel assembly which was fabricated prior to the production of mixed oxide fuel for ''Fugen'' in the Plutonium Fuel Fabrication Facility in PNC. The fuel assembly was irradiated in the Winfrith steam generating water reactor (WSGHWR) to the peak burnup of 8690 MWd/tMO. The post-irradiation tests were carried out in Windscale Nuclear Power Development Laboratories, UKAEA, from December, 1977, to June, 1978. The summary of design data of the fuel assembly is shown. The assembly was loaded into the reactor on October 21, 1975, and the irradiation was performed up to 360 effective full power days. The reactor operation of 30 cycles was carried out during the irradiation. The irradiation was successfully completed without major problems. As the post-irradiation tests, nondestructive examinations, neutron radiography, the measurement of fission gas release, the metallography of pellets and claddings, the measurement of fuel density, burnup analysis, hydraulic pressure test and burst test are reported. The failure and defect of fuel pins were not found. The design and fabrication of this fuel assembly seemed adequate. (Kako, I.). Yokouchi,-Yoji; Yokosawa,-Naoki; Kajiyama,-Takashi; Kiyonaga,-Yoshiharu; Yumoto,-Ryozo (Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works)

In pile loops for studying organic coolants.

Flowsheets and the main characteristics of X-7 and U-3 Canadium in-pile loops for studying organic coolants are considered. The X-7 loop of the NRX reactor is intended for the testing the reactor fuel elements with organic coolants, for studying the properties of the coolants based on terphenyl mixtures, and for studying the deposits formation process (fouling) on the heat transferring surface of the reactor core. The experimental program on the U-K loop of the NRU reactor implies testing of the full-scale prototype fuel elements and new more perfect technological devices and coolant purification systems in order to reduce the coolant fouling potential. A conclusion is drawn that the reactor in-pile loops are a necessary and relatively inexpensive convenient and flexible research device for testing both the fuel elements and the full-scale assemblies of nuclear reactors with organic coolants, and for simulating and working out foulingless thermal regimes of the coolant. Burukin,-V.P.; Rizvanov,-V.K.

Sensitivity calculation for fast reactors by generalized perturbation theory.

A method for sensitivity calculations to be used in a Fast Reactor Project at IEN (Nuclear Engineering Institute) is developed. (E.G.) Santo,-A.C.F.-de (Instituto de Engenharia Nuclear, Rio de Janeiro (Brazil)

Calculational studies of transients and emergency regimes during fast reactor operation and their role in safety assurance.

Methods for calculation of transients in nuclear power plants with fast reactors and practical applications of these calculations are reviewed. Calculation of the reactor core, heat exchanger, pipeline and mixing chamber dynamics is considered. The ways of calculational result application for determination of the necessary parameters of emergency protection and operational restrictions are considered. Methods for solving the problem of thermal shock in fast reactors, difficulties in emergency cooling and the ways of their overcoming are described. Bagdasarov,-Yu.E.; Kuznetsov,-I.A.

Prospects of last reactor use.

The role of fast reactors in the future power supply, their fuel cycle, influence on environment and alternative fuel cycles are considered using the materials of the International program of nuclear fuel cycle evaluation (November 1978 -8 February 1980). A comparative analysis of fast and thermal reactor economics is presented. The data characterizing the fuel breeding and burnup in the FBR type reactors with oxide- and metallic fuels for the core homogeneous and heterogeneous configurations are given. It is supposed that by 2000-2025 the breeding ratio for the FBR type reactors is to reach 1.32 at a doubling time of 17.3 h. The external fuel cycle duration is estimated to be 1 year. It is concluded that putting into operation of 100 FBR type reactors would lead to decrease in requirements for uranium by 2025 approximately 4 times, as compared with using the LWR type reactors without fuel recycling. Chechina,-O.A.; Raevskij,-I.I.

Theoretical studies aiming at the IEA-R1 reactor core conversion from high U-235 enrichment to low U-235 enrichment.

The research reactors, of which the fuel elements are of MTR type, functions presently, almost in their majority with high U-235 enrichment. The fear that those fuel elements might generate a considerabLe proliferation of nuclear weapons rendered almost mandatory the conversion of highly enriched fuel elements to a low U-235 enrichment. As the IEA-R1 reactor of IPEN is operating with highly enriched fuel elements a study aiming at this conversion was done. The problems related to the conversion and the results obtained, demonstrated the technical viabilty for its realization. (E.G.). Frajndlich,-R. (Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo (Brazil). Centro de Operacao e Utilizacao do Reator de Pesquisas)

Thermohydraulic and physical aspects of nuclear power fluidized reactor.

A nuclear power reactor that is being developed based in fluidized bed theory, is described. Some advantages of this power reactor upon other existing types, as that of pressurized water (PWR), are presented. (E.G.). Sefidvash,-F. (Rio Grande do Sul Univ., Porto Alegre (Brazil). Dept. de Engenharia Nuclear)

Testing the device angular resolution by means of -scattering.

An experimental method determining the device angular resolution has been proposed to found out an accuracy in measuring angles in the process of nuclear scattering. The method has been tested at the device designed for the measuring of full and differential cross-sections of particle nucleus interaction. The device consists from 2 multiwire chambers and scintillation counters. The device has been irradiated with the muon beam. The obtained results permitted to find errors in coordinate determination with proportional chambers and to check up experimentally the validity of the calculation of multiple scattering according to the Monte Carlo method. Chernyshev,-V.P.; Bysheva,-G.K.; Vajsenberg,-A.O.; Gol'din,-L.L.; Semenov,-A.V.; Tumanov,-G.K.

Instrument evaluation no. 29. Nuclear Enterprises PDR3 dose rate meter.

The Nuclear Enterprises PDR3 is a portable battery powered instrument covering a dose rate range from 0.5 mrad h sup - sub 1 to 50 rad h sup - sub 1 in air and a dose range from 0 to 4 rad in air. The detector is a Geiger Muller tube provided with a Nuclear Enterprises designed energy compensation sheath. The instrument is manufactured by Nuclear Enterprises Ltd. A full description is given. The instrument characteristics have been evaluated. The results are summarized and compared with the relevant requirements of the International Electrotechnical Commission for exposure rate monitors. Radiation, electrical and mechanical characteristics were examined, also environmental effects of temperature and humidity. (U.K.). Burgess,-P.H.

Time focussing and resolution in resonance detector neutron spectrometers.

Nuclear recoil produces a variation in time of arrival of neutrons scattered through different angles in pulsed-source resonance detector neutron spectrometers. The coupled variation of recoil energy shifts and of scattering angles and lengths of different paths from source to sample to detector leads to conditions on the orientation of source, sample and detector which minimize the resolution of these spectrometers. The conditions depend upon the mass of the scatterer, the excitation energy of the recoiling unit, the mean scattering angle and relative incident and scattered neutron flight paths, and apply strictly only for a single value of the excitation energy. We develop general expressions for the geometric contributions to the resolution, from which the focussing conditions emerge. The focussing effect on the resolution is significant, and is similar to that in time of flight diffractometers. (orig.). Carpenter,-J.M.; Watanabe,-N. (National Lab. for High Energy Physics, Oho, Ibaraki (Japan)

A channel profile analyser.

It is well understood that due to the wide band noise present in a nuclear analog-to-digital converter, events at the boundaries of adjacent channels are shared. It is a difficult and laborious process to exactly find out the shape of the channels at the boundaries. A simple scheme has been developed for the direct display of channel shape of any type of ADC on a cathode ray oscilliscope display. This has been accomplished by sequentially incrementing the reference voltage of a precision pulse generator by a fraction of a channel and storing ADC data in alternative memory locations of a multichannel pulse height analyser. Alternative channels are needed due to the sharing at the boundaries of channels. In the flat region of the profile alternate memory locations are channels with zero counts and channels with the full scale counts. At the boundaries all memory locations will have counts. The shape of this is a direct display of the channel boundaries. (orig.). Gobbur,-S.G. (Bhabha Atomic Research Centre, Bombay (India). Electronics Div.)

Study on the thermo-emf of the VR 5/20 thermocouples with different design.

The influence of nuclear radiations on thermo-emf ¦E (transient variations) of thermocouples widely applied for measuring the temperature up to 2000 K in vacuum in inert and carbonaceous media of the VR 5/20 thermocouples, with different design under the pulsed reactor conditions is investigated. The tests have been carried out under the reactor power providing the thermal neutron flux density of about 3.5x10 sub 1 sub 9 neutr./(m sub 2 xs), fast neutron flux density of 6x10 sub 1 sub 7 neutr./(m sub 2 xs) and radiation dose rate of 2x10 sub 6 R/s (1P=2.58x10 sup - sub 4 Kl/kg), pulse duration constituting not more than 10 s. Transient variations have been determined as ¦E=Esub(p)-Esub(0), where Esub(p) and Esub(0) are mean thermo-emf values under nominal and zero reactor power, respectively, ¦E mean square error constituting +-0.6 K. For each thermocouple type ¦E linear dependence on reactor power is obtained. It is shown that if thermal resistance between electric contact of thermoelectrodes and protective coating is negligibly small, transitient variations of thermo-emf of the VR 5/20 thermocouples are negative: from -2.5 to -5.6 K. The VR 5/20 thermocouples with insulated junction and thermocouples with ZrC protection coating have positive transient variations of the thermo-emf (5-10 K). The sign and absolute value of transient variations of the thermo-emf depend not only on radiation conditions but also on the thermocouple structure and the technique of its mounting into the object. Volkov,-E.P.; Nalivaev,-V.I.; Prijmak,-S.V.; Fedik,-I.I.; Tselykovskij,-O.P.; Yakubov,-V.Ya

Detector for recording electron spectra of nuclear gamma resonance from small surfaces of samples.

A detector for measuring nuclear gamma resonance spectra with the registration of conversion and Auge electrons from surface zones of absorbers with the radius of about 1 mm, is described. The detector is done on the basis of a gas-filled avalance detector in which the absorber is used as a cathode. The anode is done in the shape of a needle and is fixed vertically above the sample. Detector resolution in the surface is improved due to its location in the magnetic field perpendicular to the absorber plane. An example is given of using the detector for investigation of phase composition of the surface of armco iron irradiated with a laser beam with the diameter of 2 mm. Babikova,-Yu.F.; Vakar,-O.M.; Kasimovskij,-A.A.; Petrikin,-Yu.V. (Moskovskij Inzhenerno-Fizicheskij Inst. (USSR)

Double nuclear magnetic gamma resonance spectrometer.

The spectrometer is designed for investigating the effect of high-frequency magnetic fields on the spectra of nuclear -resonance in sub 1 sub 8 sub 1 Ta. Magnetic high-frequency field (2.2-4.6 MHz) in the operating volume approximately 0.5 cm sub 3 achieves the amplitude of 360 E. The main nodes of the device are described, such as -resonance spectrometer on the base of analyzer, high frequency generator, control block providing the reconstruction of generator frequency synchronously with switching of analyzer channels and the necessary registration regimes. Cheremisin,-S.M.; Dudkin,-A.Yu.

Removal of iodine species with concentrated nitric acid, (7). Iodine treatment by nitric acid decomposition.

For the Iodox process, which is atrractive for the iodine removal from off-gas stream in nuclear fuel reprocessing, a new iodine treatment process has been examined by laboratory-scale experiment. The process includes the step of stripping iodine from solution by the nitrogen oxide produced from nitric acid with formaldehyde, formic acid or sucrose. (1) As nitric acid is decomposed from azeotropic composition to 12N, about 90% of I sup 2 is evolved from the solution of IO sup 3 sup -. (2) The addition of formaldehyde or formic acid as a decomposing agent lowers the iodine residue in solution to less than 1% with the progressing decomposition of nitric acid to about 2N. (3) With sucrose as a decomposing agent, it takes a few hours to complete the reaction, which results in iodine reflux from a condenser. (J.P.N.). Kaneko,-Hisao; Komaki,-Jun; Muramoto,-Hideaki; Takeda,-Hiroshi; Hoshino,-Tadaya (Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works)

Development of vitrification of HLLW by Joule-heated ceramic melter. Process testing and components examination of the equipment.

In order to establish the vitrification process for high level liquid wastes, the development of Joule-heated ceramic melters has been performed for three years. This ceramic melter can convert continuously the mixture of nuclear wastes and glass into stable glass products. In order to perform the process testing with simulated calcined wastes and simulated denitrated liquid wastes, an engineering scale melter was made, and five running tests were carried out for about 300 days. The service life of the refractories and electrodes was evaluated from the results of these tests. The improvement of the glass flowing-out system was made in this period. The ceramic melter consists of the melting cavity, the riser and the forehearth for glass refining. Electrofused and cast refractories of ZrO sup 2 -SiO sup 2 -Al sup 2 O sup 3 were used for the walls and bottoms in contact with glass. Two pairs of metallic molybdenum electrodes are in the melting cavity, a pair of molybdenum electrodes are in the riser, and a pair of SnO sup 2 electrodes are in the forehearth. The total holding capacity is about 200 litre. The start-up, steady operation, feeding in slurry state, flowing-out of glass and stopping are explained. The melter can be operated safely for more than two years. (Kako, I.). Torata,-Shin-ichiro; Kawanishi,-Nobuo; Nagaki,-Hiroshi; Tsunoda,-Naomi (Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works)

Separation of sub 8 sub 5 Kr and of sub 3 H.

Separation of krypton in fuel reprocessing off-gas: As for the radioactive gases from nuclear power facilities, it is necessary to minimize their release to the environment, particularly, in the case of long-lived sub 8 sub 5 Kr and tritium. To remove Kr, there are various methods such as porous diaphragm and liquefaction-evaporation. The gaseous diffusion through a porous diaphragm, which has already been established in uranium enrichment, is useful for the separation of gases in the off-gas treatment system of a fuel reprocessing plant. (2) Safe handling and separation technology of tritium in nuclear fusion research: In nuclear fusion research, the main process is D-T fusion reaction, presently. Therefore, in the so-called ''tritium fuel cycle'', the establishment of the technology and its associated basic research are necessary. Handling of tritium presents many difficulties due to its high specific activity, high penetration through materials, etc. (J.P.N.). Naruse,-Yuji (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)

Ideas on the treatment and disposal of radioactive wastes.

In Japan, the level of aggregate capacity of nuclear power generation is expected to reach 51,000 - 53,000 MW in 1990, 3.5 times as much as the current 15,000 MW. Nuclear power is now 13% of the total power generation, and its radioactive wastes in drums have been piled up in power station sites. With the operation of the fuel reprocessing plant in Power Reactor and Nuclear Fuel Development Corporation, high-level radioactive wastes are now accumulating. With emphasis on the management of such high-level wastes, it is considered what ideas are feasible and if the acceptance by people is possible, as follows: the features of high-level wastes and disposal scheme, energy option space scenario, the responsible parties, public acceptance on location problem, the third party liability, financing problem, international cooperation, etc. (J.P.N.). Wakabayashi,-Hiroaki (Tokyo Univ., Tokai, Ibaraki (Japan). Nuclear Engineering Research Lab.)

Solidification of low-level radioactive wastes.

In the low-level radioactive wastes from nuclear power stations, it is necessary to reduce the volume of the wastes as far as possible, and then finish them into the solids with the properties suitable to their sea or ground disposal. In Japan, for the purpose, the methods of cement and asphalt solidifications are being employed, and further the method of plastic solidification is also studied. Developed for the practical use by JGC Corporation, the asphalt and the plastic solidification methods are described, and also in this connection, the wastes to be solidified, the properties of the solids and volume reduction are explained. At present, the places of the disposal and the standards are not established yet, therefore, the research and development on the solidification should be diversified to meet any possible circumstances. (J.P.N.). Kuribayashi,-Hiroshi (JGC Corp., Tokyo (Japan)

Plastic solidification of radioactive wastes.

Over 20 years have elapsed after the start of nuclear power development, and the nuclear power generation in Japan now exceeds the level of 10,000 MW. In order to meet the energy demands, the problem of the treatment and disposal of radioactive wastes produced in nuclear power stations must be solved. The purpose of the plastic solidification of such wastes is to immobilize the contained radionuclides, same as other solidification methods, to provide the first barrier against their move into the environment. The following matters are described: the nuclear power generation in Japan, the radioactive wastes from LWR plants, the position of plastic solidification, the status of plastic solidification in overseas countries and in Japan, the solidification process for radioactive wastes with polyethylene, and the properties of solidified products, and the leachability of radionuclides in asphalt solids. (J.P.N.). Moriyama,-Noboru (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)

Method of decontaminating radioactive substances

Purpose: To decrease the exposure dose upon operation, maintenance and disassembly of a nuclear power plant by applying impact shocks to radioactive nuclides-containing oxides deposited to instruments and pipeways of the nuclear power plant and peeling off the oxides therefrom. Method: Into cleaning water for the instruments and pipeways of a nuclear power plant, particulate substances approximately of the same specific gravity as that of the cleaning water are added and circulated. The oxides containing radioactive nuclides deposited to the instruments and the pipeways are thus applied with impact shocks by the particulate substances and peeled off from the instruments and the pipeways. Then, after separating the particulate substances, the oxides in the cleaning water are filtered to clean the cleaning water. The generation of radioactive wastes can thus be supported, whereby the exposure dose upon operation, maintenance and disassembly of the nuclear power plant can be decreased. (Moriyama, K.). Saito,-Masayuki.

Method for radioactive waste solidification.

The invention relates to the treatment of low- and medium-level radioactive wastes (10 Ci/l) and other toxic materials, in particular, to their conversion into a solidified state by incorporation in an inorganic binding material. A large amount of such wastes arises from the operation of nuclear power plants. A feature of the method of solidification wastes containing radioactive isotopes and other toxic materials by mixing with granulated metallurgical slag or slag-portlandcement is that in order to produce a monolith with a high dry waste residue content suitable for safe disposal, mixing is carried out with a water-binding ratio of 0,2-0,6 and a specific binder surface of 2800-4000 cm sub 2 /g where the temperature of the wastes being solidified is 20-90 sub 0 C. Another feature of the method is that slag-portlandcement with 20-80 mass % of slag is used as a binder. Zakharova,-K.P.; Zhikol,-T.T.; Alimova,-N.V.; Pankratov,-V.L.; Shelud'ko,-V.P.; Shimarova,-L.N.

Future fuel. Staying 'clean' while fueling up for the future.

In this article Dr. P.D. Toens reports on what will happen to nuclear waste when Koeberg comes on-stream. The decay of radioactive fission products is discussed. At a plant like Koeberg about 2 000 drums of low-level waste, which can be safely manhandled and stored aboveground, is produced each year. The high-level waste that will ultimately be produced and which would need careful handling, will be about 2 - 3m sub 3 per year per 1000MW unit. The site selection programme for waste disposal of the Nuclear Development Corporation is discussed. Some of the more pertinent factors considered in site selection include: population density, mineral potential, agricultural production, climate, ecology, regional geology, geohydrological investigations and geophysical investigations. Toens,-P.D. (Nuclear Development Corp. of South Africa (Pty.) Ltd., Pelindaba, Pretoria. Dept. of Geology)

THE ROLE OF NUCLEAR DIPLOMACY

In the midst of nuclear countries and non-nuclear countries in the framework of non-proliferation and disarmament, Indonesia has played an important role. Indonesia has been actively involved in each activity at the international level to create a world free from nuclear weapons. This involvements needs to be maintained and increased in the years to come. As a large country, Indonesia should play a key role in the field of nuclear diplomacy. All of the efforts of nuclear diplomacy as mentioned
above had a clear objective to support Indonesia’s energy program, at the institution framework as well as capacity building. Indonesia’s effort is also directed to attain appropriated international public acceptance. Keywords : Nuclear diplomacy, Non-Proliferation Treaty, CTBT, NPP. Samodra Sriwidjaja Former Ambassador Indonesia for Austria.

STUDY OF GRAFT COPOLYMERIZATION OF ACRYLIC ACID.........

ONTO NATA DE COCO AND ITS APPLICATION AS MICROFILTRATION MEMBRANE. Chemical and physical modifications of membrane can be carried out by radiation induced graft copolymerization. The aim of this research is to prepare graft copolymers of acrylic acid onto nata de coco (NDC-g-AAc) by radiation and to study the performance of grafted copolymer as microfiltration membrane. Using a total dose of 30 kGy, the highest degree of grafting obtained were 209% and 142% for r (weight ratio of monomers to nata de coco) equal to 61.3 and 35.7 respectively. The increasing degree of grafting resulted in decreasing flux due to high hydrogen bonding between grafted acrylic groups and water. It was found that the degree of swelling of NDC-g-AAc membrane with r = 35.7 was higher than that of r = 63.1. The changes of chemical structure of membrane were characterized by FTIR spectroscopy which showed a new band at 1720 cm -1 attributed to the carbonyl group of acrylic acid. Keywords: Graft copolymerization, nata de coco, microbial cellulose, acrylic acid, microfiltration membrane. Tita Puspitasari1, Cynthia Linaya Radiman2; 1National Nuclear Energy Agency, Centre for the Application of Isotopes and Radiation Technology, 2Inorganic and Physical Chemistry, Faculty of Mathematics and Natural Sciences

IAEA SAFETY STANDARDS ON MANAGEMENT SYSTEMSAND SAFETY CULTURE

The IAEA has developed a new set of Safety Standards for applying an integrated Management System for facilities and activities. The objective of the new Safety Standards is to define requirements and provide guidance for establishing, implementing, assessing and continually improving a Management System that integrates safety, health, environmental, security, quality and economic related elements to ensure that safety is properly taken into account in all the activities of an organization. With an integrated approach to management systems it is also necessary to include the aspect of culture, where the organizational culture and safety culture is seen as crucial elements of the successful implementation of this management system and the attainment of all the goals and particularly the safety goals of the organization. The IAEA has developed a set of services aimed at assisting it’s Member States in establishing, implementing, assessing and continually improving an integrated management system. Keywords : Safety Standards, Safety Culture, Management System. Kerstin Dahlgren Persson. International Atomic Energy Agency, Department of Nuclear Energy

DEVELOPMENT OF PYROCHEMICAL REPROCESSING OF THE SPENT.....

NUCLEAR FUEL AND PROSPECTS OF CLOSED FUEL CYCLE. Molten- Salt Reactor(MSR) is a design of an advanced reactor system from the GEN IV family working in thermalor epithermal neutron spectrum and using thorium or transuranium fuel in the form of moltenfluorides. It is based on the experience with the development of the molten-salt reactortechnology in the Oak-Ridge National Laboratory in the United States.The MSR fuel cycle with integrated reprocessing represents one of the potential ways both forsignificant decrease of total amount of radioactive wastes for final deposition and forutilization of nuclear energy for electricity and heat production as effectively as possible.There are two pyrochemical reprocessing techniques studied in NRI Rez plc which areconsidered to be applied both for reprocessing of already existing spent fuel and forpreparation and „on-line“ reprocessing of MSR fuel: (i) the Fluoride Volatility Method(FVM), which performs chemical conversion of spent thermal oxide fuel components intofluorides and their consequent separation by means of their different volatility, thermalstability and chemical affinity to various sorbents; and (ii) electrochemical separation of theactinides (Ans) and fission products (FP), represented mainly by lanthanides (Lns), from eachother by electrolytic deposition method on solid cathode in molten fluoride media.Keywords : Pyrochemical Reprocessing, Spent Nuclear Fuel, Closed Fuel Cycle, MoltenSalt Reactor. R. Tulackova, K. Chuchvalcova-Bimova, M. Precek,M. Marecek and Jan Uhlir; tulackova@ujv.cz

Allelism Studies On F1 Progency Of Some Dwarf And Semi-Dwarf Rice Mutants

The role of dwarf or semi-dwarf gene (s) in increasing rice production is quite well known. However, the existing gene sources for dwarf or semi-dwarf are still very limited. Some dwarf and semi¬dwarf mutants have been produced in Indnesia, e.g. mutant No. A23/PsJ/72K, A13/PsJ/72K. A3/PsJ/72K and C29/PsJ/72K which were derived from Pelita 1/1; mutants No. A227/1. A227/3. B15 and 16-B6 which were originated from A23/PsJ/72K and a dwarf mutant No. M362 induced from "Seratus Malam" upland rice variety. By crossing with Acc 123 which carrying Dee-Geo-Woo-Gen (DGWG) gene, or with a semi-dwarf variety IR 36 which has unidentical gene with DGWG gene, the gene (s) controlled dwarf or semi-dwarf characters in the mutant. were studied through the reflection occured in F 1 phenotype. The result obtained showed that there were two genes identified were not identical with DGWG gene, viz. a semi¬dwarf gene of A227/3 and a dwarf gene of M362. The dwarf gene ofM362.was also not iden¬tical with the semi-dwarf gene of IR 36. Although dwarf gene of C29/PsJ/72K was not iden¬tical with the semi-dwarf gene of IR 36 or the dwarf gene of M362, it has not been proved whether it is also not identical with DGWG gene. Riyanti Sumanggono

Analysis of Passive Moderator Cooling System of Candu-6A Reactor at Emergency Condition

Analysis of passive moderator cooling system subject to in-core LOCA with no emergency core cooling injection has been done. In this study, the new model of passive moderator system has been tested for emergency conditions and CATHENA code Mod-3.5b/Rev1 is used to calculate some parameters of this passive moderator cooling system. The result of simulation show that the proposed moderator cooling system have given satisfactory result, especially for the case with 0.7 m riser diameter and the number of heat exchanger tubes 8100. For PEWS tank containing 3000 m3 of light water initially at 30 o C and a 3641 m2 moderator heat exchanger, the average long-term heat removed rate balances the moderator heat load and the flow through the passive moderator loop remains stable for over 72 hours with no saturated boiling in the calandria and flow instabilities do not develop during long-term period.passive moderator cooling system, in-core loss-of-coolant-accident, moderator heat exchanger, passiv. Efrizon Umar, M.Hadid Subki

A Modified Second Born Approximation in Scattering by Spherically Symmetrical Central Potential

A modified second Bron approximation is investigated. Comparisons with other Born, and exact calculations, are given for promblems of scattering by a spherical central potential. The choise of parameter which is argued by Garibotti and Massaro (4) and Woolings and Mc Dowell (8) from those of simplified second Born approximations by Holt and Moiseiwitsch (5) can be chosen easily in this case of our example. B. Santoso

A Tem Investigation on Intermetallic Particles in Zircaloy-2

A TEM investigations were conducted on the heat treated zircaIoy-2 having the composition of Zr containing 1.6 % Sn, 0.2 % Fe, 0.1 % Cr and 0.05 % Ni (% wt) in order to study the characteristics of intermetallic particles related to the microstructural basis on the corosion effect. Forged zircaloy-2 was annealed in the p-phase at 1050°C for various durations, followed by water quenching. The p-quenched specimens were then annealed isothermally in the a-phase region at 650 and 750°C, followed by water quenching. The size distribution of intermetallic particles showed a tendency as the coarser become the precipitates, the lower becam their number. By increasing the annealing temperature, the growth of precipitates became more profound than by increasing the annealing time. The kind of precipitates formed in this zircaloy-2 were of the Zr(Cr,Feh and Zr2(Fe,Cr,Ni) types. These kinds of precipitates and the ratios of Fe/Cr were independent of size and shape of precipitates and annealing time and temperature in the a-phase region. Harini Sosiati Sudarminto, Noriyuki Kuwano, Kensuke Oki,

Development of Pyrochemical Reprocessing of the Spent Nuclear Fuel And Prospects of Closed Fuel Cycle

Molten-Salt Reactor (MSR) is a design of an advanced reactor system from the GEN IV family working in thermal or epithermal neutron spectrum and using thorium or transuranium fuel in the form of molten fluorides. It is based on the experience with the development of the molten-salt reactor technology in the Oak-Ridge National Laboratory in the United States. The MSR fuel cycle with integrated reprocessing represents one of the potential ways both for significant decrease of total amount of radioactive wastes for final deposition and for utilization of nuclear energy for electricity and heat production as effectively as possible. There are two pyrochemical reprocessing techniques studied in NRI Rez plc which are considered to be applied both for reprocessing of already existing spent fuel and for preparation and „on-line“ reprocessing of MSR fuel: (i) the Fluoride Volatility Method (FVM), which performs chemical conversion of spent thermal oxide fuel components into fluorides and their consequent separation by means of their different volatility, thermal stability and chemical affinity to various sorbents; and (ii) electrochemical separation of the actinides (Ans) and fission products (FP), represented mainly by lanthanides (Lns), from each other by electrolytic deposition method on solid cathode in molten fluoride mediaPyrochemical Reprocessing, Spent Nuclear Fuel, Closed Fuel Cycle, Molten Salt Reactor. R. Tulackova, K. Chuchvalcova-Bimova, M. Precek, M. Marecek, Jan Uhlir

Preliminary Safety Assessment of Hyphotetical Near Surface Disposal at Serpong Site: Near-Field Modeling

The near field modeling of a hyphotetical surface disposal at Serpong site has been performed. Considering a realistic downward water flux of 10 -10 m/ s throught the conditioned waste zone and the concrete barriers, transport of radionuclide by advection and dispersion below the bottom of the repository was calculated using PORFLOW computer code. The result shows that the highest fluxes were observed H-3, Cs-135, Nb-94 and Ni-59, all about 10 4 Bq/ a/ m 2 . Intermediate fluxes were obtained for Cs-137, I-129 and Co-60. Lowest were due to Ni-63 and C-14. The effect on radionuclide fluxes by having an unsaturated soil of 1.0-m depth below the bottom of the repository also was investigated. The results indicated that the highest fluxes were due to Cs-135, Nb-94 and Ni-59, approximately 10 4 Bq/ a/ m 2 . The fluxes owing to H-3 had decreased to 10 -9 Bq/ a/ m 2 owing to decay. Radionuclides that were not absorbed onto lateric clay soil, C-14 and I-129 did not decrease in flux. All other radionuclides had significantly smaller fluxes compared to the ones calculated at the bottom of the repository. This indicates that the lateric clay soil at Serpong site plays an important role in retarding and dispersing the radionuclide migration towards the ground water. E. Lubis, D. Mallants, G. Valckaert

Evaluation of a commercial SPECT system for quantitative tomography

Emission computerized axial tomography, ECAT, gamma camera systems are now available commercially from several manufacturers. To be cost effective the gamma camera must also be used for standard radionuclide imaging. Physical evaluation of these systems in tomographic mode is still somewhat of an art rather than a science since the performance of the equipment in tomographic mode depends to a large extent on the skill of the operator and his knowledge of the entire tomographic reconstruction process. This paper attempts to describe and explain the procedures involved in producing ECAT images using the gamma camera. The interelationships of the relevant parameters are indicated. Physical evaluation of the process is illustrated using a commercially available system, in particular the ability to produce quantitatively accurate reconstructions of clinically relevant data. The gamma camera is the 40 cm field of view Maxicamera/61 400T (IGE Ltd.) and the image processor if the IMAC 7310 (ADAC/CGR Ltd.). Keyes,-W.I. (Cumberland Infirmary, Carlisle (UK))

PENGALAMAN MENGEVALUASI USULAN ANGKA KREDIT JABATAN FUNGSIONAL PENGAWAS RADIASI.

Dalam rangka memberikankesempatan yang lebih luas pembinaan karier pegawai negeri yang bekerja dalam bidang pengawasan radiasi,Pemerintah telah menerbitkan Keputusan Menteri Pendayagunaan Aparatur Negara No. 31 tahun 1990. Walaupun jenjangini berlaku secara umum bagi pegawai negeri di Indonesia, namun kenyataannya hanya dinikmati sebagian kecilpegawai negeri dan inipun oleh mereka yang bekerja di lingkungan instansi Badan Tenaga Atom Nasional. Namundemikian jumlah pejabat fungsional pengawas radiasi dalam beberapa tahun terakhir ini nampak menurun. Pendidikandan pelatihan hanya salah satu upaya yang dapat digunakan untuk meniti jenjang karier dalam jabatan fungsionalPengawas Radiasi, tetapi mempunyai peran penting dalam pembinaan tenaga fungsional pengawas radiasi. Moendi poernomo

Conditional risk assessment of SNR 300 in case of an unprotected loss of flow accident.

This paper gives a summary of a risk study assuming unprotected loss of flow (ULOF) in the SNR 300. This study was initiated in 1979/80 by the Karlsruhe Nuclear Research Center and performed in close cooperation with Science Applications Inc., Palo Alto, USA, and Interatom Company. Part of the results also was integrated in the 'Risk Related Analysis for the SNR 300' carried out by the Gesellschaft fuer Reactorsicherheit. The character of the study described here is similar to other risk studies like the Reactor Safety Study and the German Risk Study for Nuclear Power Plants. The objectives and the methodology of the analyses are described and its results are discussed. (orig./RW). Schikorr,-M. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik); Rumble,-E.

Judicial action and technical risk.

In this study it is examined how the judiciary deals with those sections that are crucial for the use of nuclear energy. The authors get down to the pre-dominant problem of the law relating to technical safety. In the process they encounter the central dilemma of modern democracy, i.e. the strained relations which exist between judicial control and democratic responsibility. Since nuclear energy entered the market place, it has been the administrative courts which - in practice - have decided whether and to what extent nuclear energy may be used. On the one hand, this is a result of the fast growth of, and rapid change in, science and technology. On the other hand, it is a result of administrative law standards which have developed in the Federal Republic of Germany after World War II. The former requires the normative structure of the atomic law, the latter postulates how to deal with it. Legal protection against an act of public authority is guaranteed by the Basic Law and usually with some justification considered a splendid achievement of our state which is based on the rule of law. It has lead to developments in the atomic law and in many parts of the law relating to technical safety on which opinions are divided. In a dogmatic manner it has been legally examined to what extent an extensive review competence of the judiciary is a must, and whether there are any possibilities of judicial control of acts of public authorities without having to interfere with the original competence of administrations. (orig./HP). Buiren,-S.-van; Ballerstedt,-E.; Grimm,-D.

Introduction of new methods of analysis to promote the study of environment.

The particle-induced X-ray emission (PIXE) analysis has been widely used for trace element analysis. This paper introduces the characteristics of PIXE method, and some examples of analyses of environmental samples. The characteristics of the PIXE method are high sensitivity analysis, simultaneous multi-element analysis, scanning analysis, electron microscope analysis, and chemical form analysis. Two international conferences were held to discuss the problems on the PIXE method. Eighty three facilities in the world are engaged in the PIXE analysis. In Japan, the application to the material science has been made at 6 facilities. Recently, the application to biological and medical sciences has also been done. It is possible to obtain the distributions of trace elements in matrix by using a collimated beam. The beam can be collimated to a diameter of several micron with an electromagnetic lens. A PIXE spectrum of Hizikia fusiforme taken at the Cyclotron-Radioisotope Center, Tohoku University, is presented. (Kato, T.). Ishikawa,-Masafumi (National Inst. of Radiological Sciences, Chiba (Japan))

Proton beam therapy by the spot scanning method.

A proton beam therapy system was installed at the cyclotron facility of National Institute of Radiological Science. The system consists of a beam port for horizontal proton beam therapy, a spot scanning control apparatus, and a proton therapy irradiation system. The beam in monitored by three monitoring ionization chambers. The spot scanning is controlled by a TOSBAC-40 C computer. The irradiation system comprises a range modulator, a multi-leaf collimator, and applicator, and a position-defining light source. The scanning of beam spot is made by a horizontally and a vertically deflecting electromagnets. The scanning speed at the irradiation position is about 1 cm/m sec. The uniformity of irradiation field is kept for the domain of 18 cm squares. The depth distribution of irradiation dose in water was investigated, and the dose distribution was uniform to the depth of 3.6 cm. This spot scanning system can make the irregular field irradiation, which can be made by the TOSBAC-40 C computer. The trial use of the system has been made since October, 1979. (Kato, T.). Kouchi,-Kiyomitsu; Kanai,-Tatsuaki; Matsuzawa,-Hideo (National Inst. of Radiological Sciences, Chiba (Japan)); Inada,-Tetsuo.

Examples of fundamental research and applications at small accelerations

Accelerators are facilities where fundamental research and applications develop jointly. The following are examples of an interplay between fundamental research and applications: 1. Evidence for the three body force (3BF) derived from neutron-neutron (n-n) scattering length data and nuclear data for science and technology. 2. Absence of nucleoside repair effects for neutron irradiation and the development of the neutron radiobiological facility. 3. Mathematical modeling and production of radiopharmaceuticals. Ferle-Vidovic,-A.; Kaucic,-S.; Lechpammer,-T.; Osmak,-M.; Petrovic,-D.; Rendic,-D.; Slaus,-I. (Ruder Boskovic Institute, P.O. Box 1016, 41001 Zagreb)

Shielding considerations and...........

layout of the bulk shielding for the Pulsed Neutron Generator being installed at Departmento de Energia Nuclear, Universidade Federal de Pernambuco........A pulsed neutron generator, Model A-801, fabricated by Kaman Science Corporation, USA, is described. (E.G.). Narain,-R.; Andrade-Lima,-R.-de (Pernambuco Univ., Recife (Brazil). Dept. de Energia Nuclear)

Surface and adsorbate structural studies by photoemission in the h = 50- to 500-eV range

The present status of photoelectron spectroscopy in the to 50- to 500-eV range is discussed in relation to its application to surface science. Instrumentation aspects of synchrotron radiation sources are reviewed. The direct transition model is shown to be applicable in this range with some limitations. Cooper minima and adsorbate sensitivity enhancement for h >100 eV are reviewed. A new effect: condensed-phase photoelectron asymmetry: is noted. Finally, photoelectron diffraction: another new effect: is described and evaluated. Shirley,-D.A. (Materials and Molecular Research Division, Lawrence Berkeley Laboratory; Department-of-Chemistry,-University-of-California,-Berkeley,-California)

Deposition of energy from low-energy neutrons in the ICRU tissue sphere.

This work has investigated the characteristics of the energy deposition throughout the spherical volume of tissue as a result of being bombarded with neutron beams of varying energies, all the way from 0.3 MeV down to thermal. Absorbed dose and dose equivalent values have been obtained throughout the spherical phantom having the ICRU-prescribed 4-element tissue composition. The basic studies involved broad, parallel beams; but the data were easily used to provide information on isotropic beam conditions also. Average dose values were easily determined. Except for the thermal neutron source case, all the beams studied were monoenergetic in character. The thermal neutron source had a Maxwellian distribution appropriate for room temperature (20 sub 0 C). The analyses were done by Monte Carlo on the CYBER 175 computer of the University of Illinois. Cross sections used were those in the latest ENDF/B files of Brookhaven National Laboratory. Point cross-sectional data were used except for the energy groups with group-averaged values for the cross sections. This work was supported by a grant from the US National Science Foundation. Shiue,-Y.L.

X-ray beam line at the NSLS for X-ray absorption studies in material science

The development of the Material Science EXAFS line which covers the energy range of 4 keV to >25 keV is described. The general design parameters of the line have been developed specifically for the application of X-ray absorption spectroscopy to problems in material science. The optics systems consisting of a vertically collimating SiC mirror and a unique four crystal monochromator are described along with results of extensive ray tracing studies. The two backend configurations to be used on this line will also be discussed. (orig.). Sayers,-D.E. (North Carolina State Univ., Raleigh (USA)); Heald,-S.M.; Pick,-M.A. (Brookhaven National Lab., Upton, NY (USA)); Budnick,-J.J. (Connecticut Univ., Storrs (USA)); Stern,-E.A. (Washington Univ., Seattle (USA)); Wong,-J. (General Electric Co., Schenectady, NY (USA). Research and Development Center)

Nuclear fusion research: status and prospects.

In the review of the progress of nuclear science and technology, the field of nuclear fusion research is described with emphasis on the studies in laboratories outside Japan (those in Japan are reviewed elsewhere). Nuclear fusion is still essentially in the research stage, though fusion reactor technology is now a rapidly expanding field. A commercial fusion power plant is unlikely to be built until the next century. However, by the year 2000, answers should be obtained to the questions: is fusion scientifically feasible; if so, can an economically feasible reactor be built; if it can, what is the time scale for the introduction of fusion power. The following matters are reviewed: basic principles of nuclear fusion, fusion reactors, magnetic confinement research, inertial confinement, and future tokamak research and JET. (Mori, K.). Bodin,-H.A.B. (UKAEA Culham Lab., Abingdon)

Predictive geology: with emphasis on nuclear-waste disposal.

Reviews book which primarily discusses applications of earth science to the disposal of high-level radioactive wastes. Points out that very little is said regarding practical experience with, or the epistemological foundation of, prediction in the earth and geotechnical sciences. Suggests that an in-depth examination of the difficulties of retrodiction in the earth sciences might have provided the philosophical overview missing in a volume whose title stresses predictive geology. De-Marsily,-G.; Merriam,-D.F. (Pergamon Press, Maxwell House, Fairview Park, Elmsford, New York 10523)

An experiment of high physical interest.

An experiment is reported, which firstly proves the existence of neutral weak interactions. The experiment is carried out with a 200-GeV muon beam scattered at a carbon target by means of asymmetry measurements. The schematic construction of the experimental plant NA4 in the European Nuclear Science Center (CERN) is described. Klein,-M.; Nowak,-W.D.; Riemann,-T. (Akademie der Wissenschaften der DDR, Berlin-Zeuthen. Inst. fuer Hochenergiephysik)

FLIPPER II - a new photoemission system in HASYLAB.

The detailed design of a beamline, monochromator and photoelectron spectrometer for surface science studies in the photon energy range 15-200 eV is described. The photon flux from the monochromator has been measured as a function of energy. Adequate intensity and resolution are available for a wide range of photoemission studies. (orig.). Johnson,-R.L.; Reichardt,-J. (Max-Planck-Institut fuer Festkoerperforschung, Stuttgart (Germany, F.R.))

On the assessment of radionuclide resorption from the gastro-intestinal tract of the blood.

A comparison of the resorption rates measured for the radionuclides Ce, Co, Pu, Ru, Sr and Zn as well as the vitamin B12 with the recommendations for calculation given by the SSK showed that the values used by the SSK partly are too low by orders of magnitude. The dose factors therefore no longer correspond to the international level of science. (DG). Steinhilber-Schwab,-B.; Teufel,-D. (Institut fuer Energie- und Umweltforschung e.V., Heidelberg (Germany, F.R.))

Japan fusion research activities and future plans.

In Japan, fusion research started around 1956 - 1958. The organization of fusion research is divided in two groups; i.e. laboratories and institutes attached to the Science and Technology Agency, and universities affiliated with the Ministry of Education. In the several tokamaks in Japan, the main devices in operation are JET-2 at Japan Atomic Energy Research Institute and JIPP-T 2 at Institute of Plasma Physics (Nagoya University). A heliotron, and a stellarator and inertial confinement (laser fusion) are also studied. In JAERI, JT-60 plasma (tokamak) will be fired in 1984 - 1985. The following matters are described: Japanese research history, research organization in Japan, research activities (Tokamaks, laser fusion, fusion technology and reactor study), international cooperation, future plans and perspective. (Mori, K.). Uchida,-Taijiro (Tokyo Univ. (Japan). Faculty of Engineering)

The production and development of radioisotopes

Radioisotopes production by TRIGA MARK III reactor, were supplied to users. Recently, their applications in the field of medicine, pure and applied science, agicultural studies, etc., are on the rapid increase. In 1982, 306.5 Ci (211,437 thousand Won) of non-sealed radioisotopes mainly radiopharmaceuticals and 566.6 Ci (21,291 thousand Won) of radiation sources for non-destructive test were supplied to users. The total production amount of radioisotopes has reached 232,728 thousand Won (873.1 Ci) and showed 24% increase over last year. Especially pertechnetate and technetium compounds is increased 40% over last year. Radioisotopes (sup(99m)Tc and its compounds) have been delivered to hospitals in Seoul area, not later than 9 a.m. by the early morning processing. The quality control method for sup(32)P used in studies of genetic engineering, was improved and established. (Author). Kim,-Y.K.; Lee,-J.D.; Bang,-H.S.; Han,-H.S. (and others)

Environmental and Medical Sciences Division progress report January-December, 1981.

The report is presented under the following headings: 1) radiation physics (radiation biophysics, neutron spectrometry. development of new neutron dosimeters, applied neutron dosimetry, x-ray spectrometry, gamma-ray spectrometry and development of gamma-ray dosimeters, radiation standards, environmental radiation monitoring at Culham, development of air sampling techniques for control in nuclear facilities, applied air sampling techniques. 2) The nuclear environment (U.K.A.E.A. mortality study, radioactive fallout, radionuclide in arable crops and soils, environmental studies in Cumbria, Caithness and Sutherland, radionuclide enrichment of the sea-surface microlayer and transfer to the atmospheric aerosol, artificial and natural radioactivity in lake sediments, aerosols and population exposure due to nuclear power, radiation spectrometry and the nuclear environment, computer systems development. 3) Biological science (actinides and non-radioactive dusts in rodent lungs, asbestos and man-made mineral fibre studies, uptake of toxic and trace elements by man, trace element studies in Paget's disease, measurement of gastro-intestinal bleeding using sup 5 sup 1 Cr. 4) Hazardous wastes and analytical research. 5) Non nuclear atmospheric pollution work. (U.K.). Cox,-R.A.; Carter,-T.; Gibson,-J.A.B.; Morgan,-A.; Salmon,-L.; Taylor,-M. (comps.)

EXAFS in dispersive mode.

The new method of collecting EXAFS data in dispersive mode will be recalled. Polychromatic radiation is used so that data over the entire EXAFS spectrum can be recorded simultaneously. The improved efficiency in data collection opens up the possibility of kinetic studies in material science, chemistry and biophysics. The first data obtained with a self-scanned photodiode array manufactured by EGandG Reticon (RC 256 EC/17) working at room temperature show that XANES study at a few ms time-scale can be expected since only 1.3 ms were required to collect the XANES plot of elemental Ni, the D.C.I. storage ring running at a 1.72 GeV, 250 mA positron energy and current. (orig.). Flank,-A.M. (Laboratoire pour l'Utilisation du Rayonnement Electromagnetique (LURE), Paris-11 Univ., 91 - Orsay (France); Poitiers-Univ.,-86 (France). Lab. Met. Physique); Fontaine,-A.; Raoux,-D. (Laboratoire pour l'Utilisation du Rayonnement Electromagnetique (LURE), Paris-11 Univ., 91 - Orsay (France); Paris-11-Univ.,-91-Orsay (France). Lab. de Physique des Solides); Jucha,-A.; Lemonnier,-M. (Laboratoire pour l'Utilisation du Rayonnement Electromagnetique (LURE), Paris-11 Univ., 91 - Orsay (France)); Williams,-C. (Laboratoire pour l'Utilisation du Rayonnement Electromagnetique (LURE), Paris-11 Univ., 91 - Orsay (France); College-de-France,-75-Paris.-Lab.-de-Physique-de-la-Matiere-Condensee)

Earth science developments in support of waste isolation.

Earth science issues in geologic waste isolation can be subdivided into smaller questions that are resolvable. This approach provides a mechanism for focusing research on topics of definable priority and monitoring progress through the status of issue resolution. The status of resolution of major issues in borehole sealing, interpretation of groundwater hydrology, geochemistry, and repository performance assessment is presented. The Waste Terminal Storage Program has reached a point where the selection of sites, underground testing, and emplacement of waste can proceed on a well-defined schedule. Duguid,-J.O. (Battelle, Washington, DC)

Chemical issues in nuclear waste disposal.

This review of a serious national study of nuclear waste disposal was designed to provide interested science teachers with some facts about the types of scientific and technological concerns involved in these problems. This study was done in Sweden; it involved international review, and led to a public referendum on nuclear energy. Information included related to types of nuclear wastes constituents, and assessment of a disposal method and a geologic site. Radiation safety analysis was discussed. 4 figures. 2 tables. Choppin,-G.R. (Florida State Univ., Talahassee)

What can be learned with fast neutrons

The DOE/NSF Nuclear Science Advisory Committee (NSAC) is preparing a new Long Range Plan for the development of nuclear science. This document, written as input to the Long Range Plan subcommittees; describes a number of ways that experiments with incident neutrons impact on outstanding problems in nuclear reactions and spectroscopy. It is argued that major extensions of present capabilities are required to carry out these experiments. Dietrich,-F.S

A review of some aspects of the geochemistry and mineralogy of the Witwatersrand gold deposits.

Advances in science and technology in the past two decades have stimulated not only the growth of the mining industry, but also the geological sciences. The new techniques and instrumentation available for the analysis of trace and ultra-trace elements, as well as the development of the scanning electron microscope, have made possible the study of new aspects of the Witwatersrand gold and uranium deposits. These studies have greatly enhanced the knowledge of the distribution and origin of the gold within these deposits. This paper reviews the work that was carried out during the past ten years at the Chamber of Mines Research Organization. The geochemistry of the gold, and in particular the gold-to-silver ratio, can be used to identify distribution patterns and possible provenance areas. The morphological features of gold particles showed that relatively short transport distances of 30 to 50 km prevailed, which indicates that the original primary deposits were situated close to the basin in which deposition and concentration took place. The geochemistry of the quartz and pyrite pebbles and their fluid and associated mineral inclusions can delineate distribution patterns and supply information on the nature of the primary deposits. Hallbauer,-D.K. (Chamber of Mines Research Organisation, Transvaal (South Africa)).

Survey of E-division accelerators at the Lawrence Livermore National Laboratory.

The Experimental Physics Division (E-Division) at the Lawrence Livermore National Laboratory conducts research in basic and applied nuclear and atomic physics and materials science. Most of the research within the Division utilizes one of three facilities: an intense 14-MeV neutron source, a 27-MeV cyclograaff (consisting of a 15-MeV cyclotron and a 6-MV tandem van de Graaff), and a 100-MeV electron linac. A brief description of each facility is presented with emphasis on the research capabilities presently available. Proctor,-I.D. (Lawrence Livermore National Lab., CA)

Impact of accelerators on U.S. science, technology, and productivity.

The invention and continued development of particle accelerators and the associated technology have had profound impact upon many subfields of pure and applied science and upon the overall U.S. technological capabilities. Accelerators have also found extensive application in industry to produce either new products, better products, or products at lower cost. There is great potential for science to contribute to our long term economic growth and improved productivity through aggressive development of high-technology industries. Opportunities for application of accelerators in these high technology industries exist and should be exploited. This exploitation would be aided by improved cooperative efforts between industry, universities, national laboratories, and government. Leiss,-J.E. (Office of High Energy and Nuclear Physics, U.S. Dept. of Energy, Washington, DC 20545)

Radiation defects in crystals.

The results of theoretical and experimental investigations into radiation defects in crystals are given and analyzed. Structures and properties of point defects, their effect on crystal properties as well as manifestation of the so-called subthreshold processes proceeding under radiation without formation of stable Frenkel voids are described. Problems of point defect kinetics, their interaction with dislocations and the effect of these processes on physical and mechanical properties of materials as well as on swelling under radiation are discussed. New tendencies in development of radiation material science are retraced. New techniques of investigation are discussed. Prospects for development of the theory of radiation defects and its applications to the analysis of radiation phenomena are outlined. Indenbom,-V.L. (AN SSSR, Moscow. Inst. Kristallografii); Kirsanov,-V.V. (AN Kazakhskoj SSR, Alma-Ata. Inst. Yadernoj Fiziki); Orlov,-A.N. (AN SSSR, Leningrad. Fiziko-Tekhnicheskij Inst.)

Perspectives in groundwater.

Hydrology as a science is discussed. Modeling of ground water flow is reviewed. Ground water science applications are considered. Davis,-G.H.

Internal criteria for scientific choice: an evaluation of research in high-energy physics using electron accelerators.

The economic situation of scientific research is now very different from what it was in the early 1960s when Dr. Alvin Weinberg opened the debate on the criteria for scientific choice. Annual rates of growth of 10 per cent. or more in the budget for science were then common in most Western countries, while today scientists face the prospect of no growth at all or even a decline. Some progress has also been made in developing techniques for the evaluation of the scientific performance of research groups. These two facts make it interesting to reconsider the question of scientific choice. (author). Martin,-B.R.; Irvine,-J. (Sussex Univ., Brighton (UK). Science Policy Research Unit)

Final analysis data on TMI-2 reactor coolant system and reactor coolant bleed-tank samples.

This report compiles the analytical results and sample history of four reactor coolant samples, four reactor coolant bleed-tank samples, two reactor coolant bleed-tank in situ gamma scans, and one steam generator sample obtained from TMI-2 at various times. EG and G Idaho, Inc., Exxon Nuclear Idaho Company Inc., Science Applications, Inc., and Hanford Engineering Development Laboratory performed the various analyses. Cox,-T.E.; Horan,-J.T.; Nitschke,-R.L.

The Hefei Synchrotron Radiation Laboratory (HESYRL). An 800 MeV electron storage ring and its synchrotron radiation experiment area.

A group of physicists and engineers at the University of Science and Technology of China (USTC), to which we belong, is now planning a synchrotron radiation facility. The project has recently been authorized by the Chinese Academy of Science and is going to be put in to construction at Hefei, an East-China city, in a few months. The facility will be an intermediate-energy electron accelerator dedicated to synchrotron radiation research. It will be operated by a newly-established laboratory, to be called the Hevei Synchrotron Radiation Laboratory, or HESYRL for short, and guided by the USTC. This is the first serious effort made by Chinese scientists to join the world in this flourishing and fruitful research field. (orig.). Bao,-Z.M.; Xia,-Z.L. (University of Science and Technology, Hefei (China))

Computer-aided systems analysis of tumor treatment.

In this contribution the attempt is made to apply methods of systems analysis, control theory and computer science to the process of abnormal (malignant) cell growth. The modelling approach starts on the basis of experimentally gained data of normal cells and tumor cells. Complicated algorithms are developed step by step describing the division of an individual cell as well as the interactions among the single cells. The time behaviour and the spatial (three-dimensional) tumor growth are simulated with a large digital computer. The main goal of the simulation under consideration is to study different methods of tumor treatment (surgery, radiotherapy, chemotherapy) and to determine an optimum method and time of therapy prior to clinical treatment. The proceeding is discussed in detail by illustrative examples. (orig.). Duechting,-W.; Vogelsaenger,-T. (Gesamthochschule Siegen, Gummersbach (Germany, F.R.). Lab. fuer Steuer- und Regelungstechnik)

Hydrogeology of radioactive waste isolation: the challenge of a rational assessment

Plans to isolate radioactive waste raise more questions than can be answered within the lifetime of today's researchers. The existence of a multitude of unanswered questions, however, is not a unique phenomenon related to waste isolation, but is a general characteristic of all science. Although most questions related to the isolation of radioactive waste are interesting scientifically, answers to only a small but critical fraction of the questions are vital to the practical aspects of the problem. Almost all hydrogeologic evaluations of repository sites convey an excessively negative view with respect to geologic processes. Repositories do not necessarily become more hazardous with time. Many slow, normal geologic processes will seal and cover repository sites, making radionuclide migration less likely in the future than at present. Furthermore, several more rapid geologic processes, which are viewed with great apprehension, will not always have negative effects. Faulting could block ground-water circulation near the repository and consequently slow the outward migration of radionuclides; volcanism could cover repository sites, with only a slight chance of a volcanic vent contracting the radioactive waste; and in most of the northern part of the Midwest, future glacial activity would probably plaster the ground surface with layers of till, thus helping to isolate and protect any potential deep repository. Safety of waste repositories will depend on multiple barriers to migration of radionuclides. Further research focused on each barrier, however, is required before repository safety is assured. Davis,-S.N. (Univ. of Arizona, Tucson)

Surface physics with slow positrons.

Recent progress in slow beam studies of positron-surface interactions is reviewed. The key physical phenomena are introduced, and the present knowledge of the parameters involved is reviewed. The potential of the slow positron technique for surface science is discussed. (Auth.). Nieminen,-R.M. (Jyvaeskylae Univ. (Finland). Dept. of Physics)

Optimisation of a synchrotron radiation source.

In 1978 the European Science Foundation set up an ad hoc Committee on Synchrotron Radiation and since then the Committee's two sub-groups (Machine and Instrumentation) have been developing the idea of an optimised X-ray synchrotron radiation source for Europe. The properties of different types of source element (bending magnet or special insertion) have been analysed and a storage ring lattice developed which accommodates the requisite number of each. The resulting 'Pluralistic Synchrotron Radiation Facility' is described and mention is made of a number of other important features of such a machine. (orig.). Thompson,-D.J. (Science and Engineering Research Council, Daresbury (UK). Daresbury Lab.)

The manufacturing permit criteria (draft) for the nuclear safety-related items

In accordance with the revised Atomic Energy Law, we drew up the manufacture permit criteria (draft) of major safety-related components for nuclear power plant. The principal permit criteria which are prescribed in Atomic Energy Law are as follows: 1) The manufacturer should have the technical capabilities for manufacturing nuclear components. 2) The manufacturer should establish the quality assurance program which is adopted the requirements for quality assurance provided by the Minister of Science and Technology. This study was done to prepare a draft of the manufacture permit criteria which will be notified by the Minister of Science and Technology. (Author). Park,-J.S.; Kim,-H.Y.; Song,-S.H. (Korea Advanced Energy Research Inst., Seoul (Republic of Korea)); Huh,-S.J.; Shin,-D.E. (Korea Electric Co., Seoul (Republic of Korea))

Breakthrough in fracture mechanics

Fracture mechanics, the science of calculating material characteristics, stress, and flaws in plant equipment to evaluate structural integrity, usually spares the owners of nuclear power plants unnecessary expense. Instead of replacing equipment prematurely or waiting for costly, unscheduled materials failures that can take months to repair and cost thousands of dollars a day for replacement power, utilities use fracture mechanics techniques to carefully consider their options. If analyses show repair is unnecessary, plant operation can confidently be resumed. If repair is required, it can either be done immediately or, if deferrable, be scheduled for a later, more convenient outage. Lihach,-N.

Hadronic multiplicity distributions: example of a universal stochastic process.

The existence of approximate scaling of hadronic charged multiplicity distributions when plotted in KNO form (i.e., anti n P/sub n/ vs. n/anti n) continues to attract interest. Both the existence of the phenomenon, and the shape of the scaling curve psi (n/anti n) = anti n P/sub n/ (large n, anti n) has been explained from many geometrical-dynamical points of view. Here we propose instead that these results depend on a generic framework independent of dynamical details, which context moreover occurs in many areas of science. This view imposes global constraints on any modelistic view which must be respected as are the symmetries of a theory. What one learns from the existence of scaling and the form of psi is indeed interesting but different from traditional views. Carruthers,-P.

SISTEM ENERGI NUKLIR DAN KONSEP KEBERLANJUTAN

Dalam Laporan Brundtland 1987, Our Common Future,memperingatkan dunia terhadap perlunya segera melakukan langkahmaju ke arah pembangunan ekonomi yang berkelanjutan tanpamenghabiskan sumber daya alam atau membahayakan lingkungan.Berdasarkan laporan yang ditulis oleh kelompok politisi, pegawai sipildan para ahli internasional tentang lingkungan, laporan tersebutmendefinisikan pembangunan berkelanjutan sebagai berikut:Pembangunan untuk memenuhi kebutuhan generasi saat ini tanpamengorbankan kemampuan generasi mendatang untuk memenuhikebutuhannya.Laporan Brundtland menyebutkan bahwa untuk menjamin keadilanglobal diperlukan pertumbuhan ekonomi dan berargumentasi bahwapertumbuhan dimaksud hanya dapat berkelanjutan jika dicapai secarasimultan dengan melindungi lingkungan dan menghemat cadangansumber daya alam tak terbarukan. Laporan tersebut juga menyebutkanbahwa pencapaian terhadap keadilan global dan pertumbuhan yangberkelanjutan mensyaratkan perubahan teknologi dan sosial, misalnyanegara berkembang seperti Indonesia selain harus diberi kesempatanuntuk memenuhi kebutuhan dasar mereka terhadap lapangan kerja, pangan, energi, air dan sanitasi tetapi lingkungan dan cadangan sumberdaya alam dunia harus juga dihemat dengan mengubah secara bertahappengembangan dan penggunaan teknologinya.

PENGARUH BEBERAPA PARAMETER TERHADAP PROSES ELEKTROPLATING UNTUK PEMBUATAN SASARAN DALAM U-235

Proses plating adalah salah satu tahap yang pentingpada proses penyediaan sasaran U-235 untuk proses produksiradioisotop melalui reaksi pembelahan U-235. Sebelum prosesplating tahap-tahap untuk penyediaan sasaran adalah, prosespelarutan U-235/pembuatan larutan feed, proses pembuatanlarutan plating dan proses pickling/prosestabung sasaran.pengkasaranProses plating sendiri dibagi menjadi beberapa tahappenting yaitu proses elektroplating, proses striping danpirolisa, proses dekontaminasi, proses pengelasan serta testkebocoran tabung sasaran. Proses elektroplating adalah proses pelapisan/penempe-Ian Uranium pada permukaan dalam tabung sasaran. Proses Inldilakukan dengan metode elektrolisa di dalam bejana penangasaIr pada temperatur 93°C. Sebagai anoda digunakan karbon,dan katoda adalah tabung stainless steel yang sekaligusberfungsi sebagai target sasaran, dan sebagai elektrolitadalah larutan elektroplating.

PERSEPSI MASYARAKAT TERHADAP PEMBANGKIT LISTRIK TENAGA NUKLIR (PLTN)

Preliminary research on the perception and resistance of the people concerninggovernment's plan to build a nuclear power plant for electricity at Muria peninsula, in Jepara,has that some people refused, some were ready to accept, and somejust he!s'itated.In generalthe beaurocrats accepted the plan, although some felt doubtful since they are in change ofenvirontment conservation. Parliament members and religious leaders have the tendency to bedoubtful in response of the goverment's plan on nuclear power plant. Those NGO members,especially theSe under young aclivist' leaders have refused the plan, while other religiousleaders and some rural leaders tend to accept-it.The various perception and attitudes which exist in the society are Inostly caused byconditions such as one's position, his group's perception in which he attached to, and factorseither socio-cultural, socio-political, or socio economics. Especially those with negativeperception were actually influenced by thefeeling of distrust to the government. 'At this time the government is trying to rebuild people's confidence by planning somedevelopment programs with bottom-up approach, but since it has a bad reputation in the post,that different attitudes have emerged toward state's projects, since in the past many personshave corrupted the project they carried-out for their own benefit,The various attitudes of the people toward the government have their impact on thegovernment plan to build nuclear plant in Jepara. In this situation it will be more who reject theplan. To this moment is seems that the government has not succes.sfully changhd its image tohave public trust, due to their prejudice to government projects, more over for its nuclearpowerplant. Input of informafion, especially about nuclear. They select information aboutnuclear mostlyfrom the negative side only, although there should be also positive side. A. M. Djuliati Suroyo; Pusat Penelitian Sosial Budaya, Lembaga Penelitian Universitas Diponegoro (UNDIP)

Recent work using the ANL HVEM-ion beam interface.

The ANL-Materials Science and Technology Division High Voltage Electron Microscope-Tandem Facility is a unique national research facility for in-situ studies of the interaction of energetic particle with solids. The ion-beam interface permits ion beams from either a 300-kV Texas Nuclear or a 2-MV National Electrostatics Tandem accelerator to be transported into the stage of our Kratos EM7 1.2-MV HVEM. The current status of research projects employing the ionbeam interface is reported. Taylor,-A.; Ryan,-E.A. (HVEM-Tandem Facility Materials Science and Technology Division, Bldg. 212, Argonne National Lab, 9700 S. Cass Ave., Argonne, IL 60439)

Vanadium oxides. Chemical preparation, properties, application.

The subject is covered under the following headings: chemical preparation of vanadium oxides, characterization of vanadium oxides, physical properties of vanadium oxides, and application of vanadium oxides in science and engineering. Brueckner,-W.; Oppermann,-H.; Reichelt,-W.; Terukov,-J.I.; Tschudnovski,-F.A.; Wolf,-E.

IAEA 25 th anniversary

Establishment history and main evolution stages of the IAEA are considered. The USSR active participation in the IAEA activity is underlined. The IAEA activity covers a wide range of problems including problems of nuclear power development, technical assistance for countries in training of national personnel and development of scientific researches as well as issues of control for using nuclear materials, equipment and technology. The IAEA coordinates and carries out a large volume of investigations into nuclear power economies, reactor physicals and NPP technology, nuclear fuel cycle with provision for ecological aspects giving much attention to nuclear safety. Programs related to activities of the IAEA working groups on fast liquid-metal-cooled reactors and gas-cooled reactors are of great interest. From 1978 IAEA accomplishes an extensive program on the elaboration of technical documentation concerning underground storage of radioactive wastes. Multiple data on the operational experience of most of the NPPs all over the world amounting to about 2600 reactor-years are available. One of the most important directions in the IAEA activity is data exchange, coordination and performing investigations in the area of controlled thermonuclear fusion. It is concluded that for 25 years the IAEA has traversed a long path and become a leading center of international cooperation in the area of nuclear science and engineering. Morozov,-I.G

Intense positron beams: linacs - preworkshop copy

Beams of monoenergetic positrons with energies of a few eV to many keV have been used in experiments in atomic physics, solid-state physics and materials science. The production of positron beams from a new source, an electron linac, is described. Intense, pulsed beams of low-energy positrons have been produced by a high-energy beam from an electron linac. The production efficiency, moderator geometry, beam spot size and other positron beam parameters have been determined for electrons with energies from 60 to 120 MeV. Low-energy positron beams produced with a high-energy electron linac can be of much higher intensity than those beams currently derived from radioactive sources. These higher-intensity beams will make possible positron experiments previously infeasible. Howell,-R.H.; Alvarez,-R.A.; Woodle,-K.A.; Dhawan,-S.; Egan,-P.O.; Hughes,-V.W.; Ritter,-M.W

Actuality of the Einstein theory of gravitation.

Problems of actuality of the Einstein theory of gravitation are lightened. The great Einstein theory of gravitation is shown to remain a reliable base of understanding of modern physical world pattern and its inevitable further inexhaustible precising. The main GRT difficulties are enumirated: determination of reference systems, presence of singularities in the theory, absence of consistent determination of the gravity energy, impossibility of accounting the relations between atomic, gravitational and cosmological characteristics. The attention is paid to gauge, twistor problems and to unified interaction theory. The great contribution of the soviet science in the theory of gravitation is stressed. Ivanenko,-D.D.

University-industry research collaboration.

Research and development efforts made by government, private industry and universities have transformed the United States into a major power in the world in science and technology. But our commitment in RandD has slipped in the past few years. There are growing problems in the composition of the science-engineering work force as well as our productivity. Possible long-term consequences of this worsening situation are predictable. Since government reduction in research spending plus inflation are eroding potential education and research funds, University-Industry collaboration becomes a necessity for maintaining the research activities and to reverse the worsening trend. The necessity of collaboration is well recognized by industries as well as by academia. However, the implementation of university-industry collaboration is non-trivial. What universities want is research funding with freedom to spend it. What industries want is research results which can directly apply to the innovation of new and improved products and technology, plus a continuous flux of graduating young blood to inject into industries. In this talk, the author will re-emphasize the crisis in our RandD with cold statistics. I will stress the need of university-industry collaboration and summarize and comment on some of the suggestions made to universities as well as to industries as examples in this type of collaboration. Chu,-W.K. (Dept. of Physics and Astronomy, University of North Carolina at Chapel Hill, Chapel Hill, NC 27514

UPAYA PENGAMANAN BENDUNGAN DENGAN KEMUNGKINANAPLIKASI TEKNOLOGI ISOTOP

Pembangunan prasarana pengairan, khususnyayang berskala bangunan besar seperti waduk, bendung,tanggul pengendalian banjir, dll menuntut pertimbangankeamanan struktur yang nyaris tidak dapat mentolerirkemungkinan resiko kegagalan (structural failure). Hal inidapat dimengerti mengingat betapa suatu kegagalanstruktur dati bangunan dati bangunan tersebut dapatmenimbulkan bencana bagi kehidupan manusia yangmenetap dihilir bangunan. Kasus terjadinya keruntuhanbendungan dibeberapa tempat di dunia pernah tercatatsebagai pengalaman yang mengerikan dalam sejarahperadaban manusia.Belajar dati perkembangan teknologi pengamananbendungan selama ini maka sejumlah faktor kuncikeamanan telah diidentifikasi yang memerlukanpengamatan reguler untuk memonitor kondisinya.Teknologi yang dapat digunakan untuk memonitor faktorfaktortersebut telah banyak digunakan daD beberapadiantaranya terbuka bagi kemungkinan aplikasi teknologiisotop.Makalah ini lebih diarahkan untuk menyampaikankebutuhan yang diperlukan dalam upaya pengamananbendungan-bendungan besar pengairan, khususnya untukpengamanan bendungan di Indonesia. Makalah ini tidakbermaksud untuk membahas teknologi isotopnya tetapilebih ditujukan untuk melihat kemungkinan aplikasiteknologi ini melalui pemahaman kebutuhannya yangterkait dalam upaya pengamanan bendungan. Dr. A. Hafied A. Gany, M.Sc; Pendayagunaan clan Pengembangan Sumberdaya Air, Ditjen. Pengairan

PROSPER ENERGI MASA DEPAN DI INDONESIA

Pembangunan energi di Indonesia diarahkan untuk mendorong kegiatanpembangunan clan peningkatan kesejahteraan rakyat untuk memenuhi kebutuhan energimasyarakat dengan menjamin ketersediaan clan peningkatan mutu serta pelayananenergi. Penggunaan energi harus memperhatikan: kelestarian sumber energi untukjangka panjang, kebutuhan energi dalam negeri, peluang ekspor, keamanan clan keselamatan masyarakat, 1Glestarian fungsi lingkungan hidup. Pengembangan energi dilakukan melalui survei, eksplorasi clan pemanfaatan sumber energi barn, peningkatan efisiensi clan efektivitas penambangan, clan pengolahan sumber energi. Untuk menjaga kelestarian sumber energi perlu diupayakan penghematan, penganekaragaman penggunaan secara optimal clan penggunaan peralatan serta teknologi hemat energldalam kerangka kebijaksanaan energi nasional yang menyeluruhclanterpadu.Salah satu visi energi yang tercantum dalam Kebijaksanaan Umum BidangEnergi (KUBE) menyatakan bahwa sumberdaya energi ter'utama sumberdayahidrokarbon adalah terbatas dimanfaatkan sebagai bahan bakar clanbahan baku industridalam negeri untuk meng~asilkandevisa.Dalam visi energi tersebut ditemukan dilema energi yaitu adanya dua pilihancara perolehan devisa; yangpertama melalui ekspor energi fosil clany.(mgkedua melaluipenggunaan sumberdaya hidrokarbon untuk meningkatkan proses industrialisasi yangmenghasilk~n produk industri. Sumber energi fosil sebagai komoditi ekspor bisa "mendapatkan devisa secara cepat clan sederhana, walaupun nilai tambahnya mungkinrelatif lebih keci!. Untuk mendapatkan cara perolehan nilai tambah ekonomi yangterbaik perlu adanya suatu analisayang tepat dan mendalam. DR. A. Harsono Soepardjo, M.Eng.; Pengkajian Energi Universitas Indonesia, Jurusan Fisika - FMIPA UI

Space-time in microcosm.

The monograph deals with a critical analysis of the space-time description of the elementary particle world. . An idea is presented to the effect that the troubles of a modern theory are related with improper geometrical representations in describing the elementary particle interactions within short ranges. A detailed analysis of the troubles is given, and some new directions connected with various modifications of the space-time relationships are outlined. Along with conventional geometrical representations elaborated by the classical science based on the macrocosm phenomena analysis, a very original outline is presented of questions concerning a description of various geometrical relationships in the microcosm: measuring coordinates and time of particles both for a relativistic and nonrelativistic case; particle localization; distribution of signals in nonlinear field theories; space-time quantization, etc. Subjects related with conditions of micro- and macrocausality in the quantum field theory are described, including many of interesting results obtained by the author, e. g. the relationship between the causality violation in minor space-time regions and the processes observed in the elementary particle scattering. Most of the results presented almost have not been published earlier. Blokhintsev,-D.I.

The hydrothermal leaching behaviour and properties of sodium-calcium aluminophosphosilicate glasses.

Glasses based on a mixture of the minerals tourmaline, bentonite, and apatite (calcium phosphate) have been prepared. These glasses can be tailored to produce leach solutions that will readily precipitate apatites and clay minerals or zeolites. The leaching properties of a glass containing Cs, Sr, and U have been studied in the presence of a geochemical buffer of apatite and bentonite. The leaching of Sr and Cs is significantly retarded in the buffer. A nuclear waste form of glass of the composition 20CaO-6P sup 2 O sup 5 -8B sup 2 O sup 3 -10Na sup 2 O-34SiO sup 2 -15Al sup 2 O sup 3 -3Fe sup 2 O sup 3 -10CuO with a melting temperature of about 1000 deg C is proposed. Melling,-P.J.; Karkhanis,-S.N.; Fyfe,-W.S.; Bancroft,-G.M. (University of Western Ontario, London (Canada). Dept. of Chemistry; University-of-Western-Ontario,-London (Canada). Dept. of Geology; University-of-Western-Ontario,-London (Canada). Centre for Chemical Physics)

Control of radioactive waste disposal into the marine environment.

The body of this publication is intended to provide adequate information on the broad aspects of radioactive waste disposal into the sea. The introduction of radionuclides into the sea from uncontrollable sources, such as weapons test explosions, is outside the scope of this publication, as are releases of radionuclides from nuclear-powered vessels. It should be stressed that agreements on practices for the marine disposal of wastes are being developed and the understanding of oceanographic processes is rapidly progressing; therefore, the conclusions presented here should always be considered in the context of changes in both knowledge and practice that occur subsequent to the completion of this text. International Atomic Energy Agency, Vienna (Austria).

Proceedings of the workshop on geological disposal of radioactive waste. In situ experiments in granite.

In the development of safe methods for disposal of highly radioactive wastes from nuclear power generation, the International Stripa Project is a key element in in-situ experimental programmes in granite. These proceedings provide an overwiew of conclusions that can be drawn from on-going research at the Stripa mine in Sweden and at similar facilities in the OECD area. Nuclear Energy Agency, 75 - Paris (France).Workshop on geological disposal of radioactive waste. In situ experiments in granite. Stockholm (Sweden).

Progress with thermomechanical investigations of the Stripa site.

The Stripa mine in Sweden has provided an unusual opportunity to investigate the thermomechanical behavior of a granitic rock mass and the effect on such behavior of the discontinuities that are a persistent feature. Experiments to simulate the thermal effects of burying radioactive wastes have been carried out at a depth of about 340m. All of the thousands of underground measurements of temperatures, displacements, and stresses in the rock, recorded continuously over this period, have been made available on digital tape and in hard copy. This paper presents some results of recent investigations. Although temperature fields predicted by calculations based on linear heat conduction compare well with measured field data, evidence for some convective heat transfer has been found. Measured values of displacements have been significantly less than those predicted by calculations. Evidence that these displacements are diminished by fractures in the granite has been found. A program of laboratory investigations has been started to measure coefficients of thermal expansion and elastic moduli for Stripa granite. USAP (Underground Structural Analysis Program) is a unique finite element program that has been developed specifically for the analysis of underground structures; it has the potential to be used effectively in general problems associated with the underground storage of nuclear waste. Cook,-N.G.W.; Witherspoon,-P.A.; Wilson,-E.L.; Myer,-L.R. (University of California, Berkeley (USA))

Results and conclusions from rock mechanics/hydrology investigations: CSM/ONWI test site.

The Colorado School of Mines (CSM) under sponsorhip of the Office of Nuclear Waste Isolation (ONWI) has established a hard rock test facility in its Experimental Mine at Idaho Springs, Colorado. The CSM/ONWI Experimental Room was driven in the jointed biotitic gneiss using carefully designed and executed blast rounds. This room is above the water table, and lies under approximately 100m of cover. Included in this paper are: the results of RQD (Rock Quality Designation) crosshole ultrasonic, permeability and deformation modulus measurements; and, an overview of the instruments selected and measurements used by Terra Tek in determining thermal and mechanical properties from a heated block experiment. Hustrulid,-W. (Colorado School of Mines, Golden (USA)); Ubbes,-W. (Battelle Memorial Laboratories, Columbus, Ohio (USA))

The nuclear-power industry.

In this article the nuclear-power industry is discussed. The future of the nuclear industry is influenced by the current economic recession and political problems. The last factor also includes the public opinion about the proliferation of nuclear weapons and nuclear safety. The present state of the nuclear power industry is reflected in the uranium market, where the decline in the uranium price is having a severe impact upon uranium production. Pavitt,-E. (General Mining Union Corp. Ltd., Johannesburg (South Africa))

Nuclear engineering modern status in China

The status of reactor engineering, fuel technology, measurement engineering, radiation protection and nuclear-technological normalizing in China is examined. The parameters of the HFETR high-flux research reactor are presented. The HFETR reactor represents a light-water reactor with beryllium reflector and maximum thermal- and fast neutron fluxes 6.2x10 sub 1 sub 4 and 5.7x10 sub 1 sub 4 neutron/(cm sub 2 xs), respectively. It is noted that during this century the installed power of the Chinese NPS will make up not more than 10 gW. Therefore, the nuclear power will not contribute significantly to the China power-supply. A considerable success in the field of the measuring equipment production has been achieved in China during the last years. The Chinese industry produces NaI(Te) detectors up to 200 m in diameter, organic scintillators with p-terphenyl, 4096-channel analysers, semiautomatic thermoluminescent dosimeters, gamma-scintillating radiometers and other equipment. Beker,-K.