Impact analysis of spent fuel jacket assemblies
Creators
- 1. Martin Marietta Energy Systems, Oak Ridge, TN (United States). Engineering Analysis
Description
As part of the analyses performed in support of the reracking of the High Flux Isotope Reactor pool, it became necessary to prove the structural integrity of the spent fuel jacket assemblies subjected to gravity drop that result from postulated accidents associated with the handling of these assemblies while submerged in the pool. The spent fuel jacket assemblies are an integral part of the reracking project, and serve to house fuel assemblies. The structural integrity of the jacket assemblies from loads that result from impact from a height of 10 feet onto specified targets has been performed analytically using the computer program LS-DYNA3D. Nine attitudes of the assembly at the time of impact have been considered. Results of the analyses show that there is no failure of the assemblies as a result of the impact scenarios considered
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1194-8
- Imprint Title
- Natural hazard phenomena and mitigation. PVP-Volume 271
- Imprint Pagination
- 169 p.
- Journal Page Range
- p. 83-86.
Conference
- Title
- 1994 pressure vessels and piping conference.
- Dates
- 19-23 Jun 1994.
- Place
- Minneapolis, MN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26021987
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; DEFORMATION; FAILURES; FUEL ELEMENTS; FUEL RACKS; FUEL STORAGE POOLS; HFIR REACTOR; IMPACT TESTS; L CODES; MATERIALS HANDLING; MATERIALS HANDLING EQUIPMENT; MATHEMATICAL MODELS; SAFETY ANALYSIS; SPENT FUEL STORAGE
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; EQUIPMENT; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS TESTING; MECHANICAL STRUCTURES; MECHANICAL TESTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; STORAGE; SUPPORTS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-940613--.