Based on SCALE code criticality safety analysis of RFA improved type fuel assembly stored in high-power passive nuclear power plant
- 1. Nuclear and Radiation Safety Center, Beijing (China)
Description
RFA improved type fuel assembly designed by Westinghouse Electric Company is applied to high-power passive nuclear power plant. The Scale code is a comprehensive modeling and simulation code suite for nuclear safety analysis and design that is supported by NRC, as well as the U.S. Department of Energy. It is established that appropriate calculation model of the spent fuel storage pool based on Scale code can be obtained. We analyzed the spent fuel pool criticality safety in normal condition and assumed accident condition with reasonable assumptions. Calculation results show that keff is 0.90129 in normal condition and keff is 0.907 93 in case of assembly drop accident of area I. The value of keff is 0.909 98 in normal condition, and the value of keff is 0.92407 in the assembly error insertion accident of area II. Both in normal condition and assumed accident condition, the values of keff are less than 0.95 in a subcritical state. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Electronics and Detection Technology
- Journal Volume
- 36
- Journal Issue
- 11
- Journal Page Range
- p. 1117-1121
- ISSN
- 0258-0934
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 53032629
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRITICALITY; DESIGN; ERRORS; FUEL ASSEMBLIES; FUEL STORAGE POOLS; MULTIPLICATION FACTORS; NUCLEAR POWER PLANTS; RADIATION PROTECTION; SAFETY ANALYSIS; SIMULATION; SPENT FUEL STORAGE; SPENT FUELS
- Descriptors DEC
- DIMENSIONLESS NUMBERS; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FACILITIES; NUCLEAR FUELS; POWER PLANTS; REACTOR MATERIALS; STORAGE; THERMAL POWER PLANTS
Optional Information
- Notes
- 5 figs., 4 tabs., 8 refs.