Interpretation of the CABRI LT1 test with SAS4A-code analysis
Creators
- 1. Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center
Description
In the CABRI-FAST LT1 test, simulating a ULOF (Unprotected Loss of Flow) accident of LMFBR, pin failure took place rather early during the transient. No fuel melting is expected at this failure because the energy injection was too low and a rapid gas-release-like response leading to coolant-channel voiding was observed. This channel voiding was followed by a gradual fuel breakup and axial relocation. With an aid of SAS4A analysis, interpretation of this test was performed. Although the original SAS4A model was not well fitted to this type of early pin failure, the global behavior after the pin failure was reasonably simulated with temporary modifications. Through this study, gas release behavior from the failed fuel pin and its effect on further transient were well understood. It was also demonstrated that the SAS4A code has a potential to simulate the post-failure behavior initiated by a very early pin failure provided that necessary model modification is given. (author)
Availability note (English)
Available from JICST Library (JICST: Japan Science and Technology Corporation, Information Center for Science and Technology), P.O. Box 10 Hikarigaoka, Tokyo 179-9810 Japan, FAX: +81-3-3979-4781 (domestic), FAX: +81-3-3979-2210 (oversea)Additional details
Publishing Information
- Imprint Pagination
- 21 p.
- Report number
- JNC-TN--9400-2001-048
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 33023527
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature, Numerical Data
- Descriptors DEI
- CABRI REACTOR; EXPERIMENTAL DATA; FAILURES; FUEL PINS; HOLLOW FUEL RODS; IN PILE LOOPS; LOSS OF FLOW; NUMERICAL ANALYSIS; S CODES; SIMULATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUEL RODS; INFORMATION; MATHEMATICS; NUMERICAL DATA; POOL TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 1 ref., 12 figs., 1 tab.