Syeilendra Pramuditya1*, Zaki Suud2, and Abdul Waris31ITB student, Bandung, Indonesia2 ITB, Bandung, Indonesia3 ITB, Bandung, Indonesia,*E-mail: syeilendra.p@gmail.com
DEVELOPMENT OF INTEGRATED SIMULATION CODE SYSTEM OF PWR EDUCATIONPURPOSE. The development of computer code for preliminary design study of PWR nuclear reactor has beenperformed. The code is named Preliminary Nuclear Plant Analysis Code or PRENPAC, it contains five maincalculation modules, that are neutronic module, core thermal hydraulic, heat transfer at steam generator, heattransfer at condenser, and thermodynamic module. The neutronic module is based on steady-state multigroupneutron diffusion equation, and also can handle heterogeneous (multiregion) core composition. In order toverify the quality as well as accuracy of calculation result of neutronic module, benchmarking to StandardReactor Analysis Code (SRAC), a code developed by the Japan Atomic Energy Research Institute (JAERI), hasalso been performed. The average difference of k-eff calculation between the two codes is below 0.5% only. Thecore thermal hydraulics module is able to calculate in-core temperature distribution, coolant density profile,coolant mass flow and flow rate, and also coolant pressure drop after passing through the core. The heattransfer module is able to calculate temperature changes of the two fluids that exchanging heat, heat transferrate, and vapor fraction; this module also could accommodate both parallel and counter flow system. Thethermodynamic module is based on Rankine steam cycle, and its main task is to calculate plant efficiency.Keywords: nuclear reactor simulation code, PWR, Rankine steam cycle, boiler, steam generator, condenser
DEVELOPMENT OF INTEGRATED SIMULATION CODE SYSTEM OF PWR EDUCATIONPURPOSE. The development of computer code for preliminary design study of PWR nuclear reactor has beenperformed. The code is named Preliminary Nuclear Plant Analysis Code or PRENPAC, it contains five maincalculation modules, that are neutronic module, core thermal hydraulic, heat transfer at steam generator, heattransfer at condenser, and thermodynamic module. The neutronic module is based on steady-state multigroupneutron diffusion equation, and also can handle heterogeneous (multiregion) core composition. In order toverify the quality as well as accuracy of calculation result of neutronic module, benchmarking to StandardReactor Analysis Code (SRAC), a code developed by the Japan Atomic Energy Research Institute (JAERI), hasalso been performed. The average difference of k-eff calculation between the two codes is below 0.5% only. Thecore thermal hydraulics module is able to calculate in-core temperature distribution, coolant density profile,coolant mass flow and flow rate, and also coolant pressure drop after passing through the core. The heattransfer module is able to calculate temperature changes of the two fluids that exchanging heat, heat transferrate, and vapor fraction; this module also could accommodate both parallel and counter flow system. Thethermodynamic module is based on Rankine steam cycle, and its main task is to calculate plant efficiency.Keywords: nuclear reactor simulation code, PWR, Rankine steam cycle, boiler, steam generator, condenser
