[3K07-09] Fast Reactor Core & Fuel 1

[3K08] Neutronics benchmark analysis of FFTF loss of flow without scram test No.13

*Kazuya Ohgama¹, Atsushi Takegoshi², Erina Hamase¹, Norihiro Doda¹, Hidemasa Yamano¹, Masaaki Tanaka¹ (1. JAEA, 2. NESI)

Keywords:Sodium-cooled Fast Reactor, Fast Flux Test Facility, Neutronics Design, Gas Expansion Module

To improve accuracy of safety design methods of fast reactors, JAEA has been participating in the IAEA coordinated research project of the benchmark analysis of FFTF loss of flow without scram test No.13. The evaluation of negative feedback reactivity of gas expansion modules which are unique and important equipment of the FFTF will be reported as well as the results of neutronics benchmark of reactivity coefficients for input data of a plant dynamic analysis.