Development of analytical code for core disruptive accident of metallic fuel core and evaluation of upper limitation of coolant void reactivity
Creators
- 1. Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan). Komae Research Lab
Description
In the event of HCDA (Hypothetical Core Damage Accident) the safety of the metallic core must be ensured. Coolant void reactivity, which produces a positive reactivity effect, must be restrained to exclude 'energetic sequence' (uncontrollable power generation). As this reactivity and the core performance are in a state of confrontation, an upper limit must be determined through safety analyses. The larger the coolant void reactivity becomes, the more the core performance improves. A core dynamics analysis code named CANIS has been developed to analysis metallic fuel properties, irradiation behavior, and transient behavior in the initiating phase of HCDA. ULOF (Unprotected Loss Of Flow) events, which are considered major HCDA initiators, are analyzed with various parameters of cladding failure conditions and molten fuel dispersion velocities. The results indicate, the cladding failure condition is the most sensitive safety parameter. The coolant void reactivity of 12$ is acceptable in the condition that cladding fails at 1,000 degC. And the upper value is limited to 8$ for the conservative condition of a 1,200 degC failure criteria. (author)
Additional details
Publishing Information
- Journal Title
- Denryoku Chuo Kenkyusho Hokoku
- Journal Issue
- no.T01002
- Journal Page Range
- p. 1-4, 1-14
- ISSN
- 1340-4652
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 33011970
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ALLOY NUCLEAR FUELS; C CODES; COOLANTS; FBR TYPE REACTORS; FUEL CANS; FUEL ELEMENT FAILURE; FUEL-CLADDING INTERACTIONS; LOSS OF FLOW; REACTIVITY; REACTOR CORE DISRUPTION; REACTOR SAFETY; VOIDS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; SAFETY; SOLID FUELS