Neutronic/Thermalhydraulic Coupling Technigues for Sodium Cooled Fast Reactor Simulations

Jean Ragusa ; Andrew Siegel ; Jean-Michel Ruggieri

关键词: ALGORITHMS;    TESTING;    SODIUM COOLED REACTORS;    FAST REACTORS;    COMPUTERIZED SIMULATION;    REACTOR KINETICS;    THERMAL HYDRAULICS;   

DOI  :  10.2172/992636
RP-ID  :  DOE/ID/14837
PID  :  OSTI ID: 992636
Others  :  TRN: US1007895

美国|英语

来源: SciTech Connect

【 摘 要 】

The objective of this project was to test new coupling algorithms and enable efficient and scalable multi-physics simulations of advanced nuclear reactors, with considerations regarding the implementation of such algorithms in massively parallel environments. Numerical tests were carried out to verify the proposed approach and the examples included some reactor transients. The project was directly related to the Sodium Fast Reactor program element of the Generation IV Nuclear Energy Systems Initiative and the Advanced Fuel cycle Initiative, and, supported the requirement of high-fidelity simulation as a mean of achieving the goals of the presidential Global Nuclear Energy Partnership (GNEP) vision.