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Development and Applications of Nuclear Design and Safety Assessment Program SuperMC for Fast Reactor

Jun 28, 2017, 5:50 PM
1h 10m
Yekaterinburg

Yekaterinburg

POSTER Track 6. Test Reactors, Experiments and Modeling and Simulations Poster Session 2

Speaker

Prof. liqin hu (Institute of Nuclear Energy Safety Technology, CAS · FDS Team)

Description

Abstract: Compared with the other reactor types, the neutron spectrum of fast reactors is hard, affecting the neutronics and safety performance, for which advanced nuclear simulation methods such as Monte Carlo method is necessary for the nuclear design. Super Monte Carlo Simulation Program for Nuclear and Radiation Process (SuperMC) is a general, intelligent, accurate and precise program for the design and safety evaluation of nuclear system including fast reactors. The latest version of SuperMC can accomplish the n, γ transport calculation and depletion calculation, and is integrated with CAD-based automatic modeling, visualization and cloud computing framework. More than 2000 benchmark models and experiments have been duly verified and validated, including the nuclear analyses of fast reactor benchmark BN600, BFS2, etc. Moreover, SuperMC has been applied in the core and shielding design and analysis of a fast reactor, the China Lead-based Research Reactor (CLEAR). Keywords: SuperMC; Nuclear Design and Safety Evaluation Program; Fast Reactors; CLEAR

Country/Int. Organization

China/Institute of Nuclear Energy Safety Technology, CAS · FDS Team

Primary author

Prof. liqin hu (Institute of Nuclear Energy Safety Technology, CAS · FDS Team)

Co-authors

Dr jing song (Institute of Nuclear Energy Safety Technology, CAS · FDS Team) Prof. lijuan hao (Institute of Nuclear Energy Safety Technology, CAS · FDS Team) Prof. pengcheng long (Institute of Nuclear Energy Safety Technology, CAS · FDS Team) Prof. yican wu (Institute of Nuclear Energy Safety Technology, CAS · FDS Team)

Presentation materials