Published 1997
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Criticality safety of storage barrels for enriched uranium fresh fuel at the RB research reactor
Description
Study on criticality safety of fresh low and high enriched uranium (LEU and HEU) fuel elements in the storage/transport barrels at the RB research reactor is carried out by using the well-known MCNP computer code. It is shown that studied arrays of tightly closed fuel barrels, each entirely loaded with 100 fresh (HEU or LEU) fuel slugs, are far away from criticality, even in cases of an unexpected flooding by light water.(author)
Availability note (English)
Available from INIS in electronic form; Also available from Institute of Nuclear Sciences VINCAFiles
38105330.pdf
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Additional details
Publishing Information
- Publisher
- Yugoslav Nuclear Society, Institute of Nuclear Sciences VINCA, Belgrade, Yugoslavia
- Imprint Place
- Belgrade (Yugoslavia)
- ISBN
- 86-7306-012-5
- Imprint Pagination
- 4 p.
- Report number
- INIS-RS--1103
Conference
- Title
- Yugoslav Nuclear Society Conference (YUNSC'96), Proceedings
- Original Conference Title
- Jugoslovensko nuklearno drustvo konferencija, zbornik radova
- Dates
- 6-9 Oct 1996
- Place
- Belgrade (Yugoslavia)
INIS
- Country of Publication
- Yugoslavia
- Country of Input or Organization
- Yugoslavia
- INIS RN
- 38105330
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINERS; CRITICALITY; HIGHLY ENRICHED URANIUM; M CODES; MONTE CARLO METHOD; R-B REACTOR; REACTOR SAFETY; SAFETY ANALYSIS; SLIGHTLY ENRICHED URANIUM; STORAGE
- Descriptors DEC
- ACTINIDES; CALCULATION METHODS; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM; EXPERIMENTAL REACTORS; HEAVY WATER MODERATED REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; NATURAL URANIUM REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; TRAINING REACTORS; URANIUM; ZERO POWER REACTORS
Optional Information
- Notes
- 5 refs., 4 figs., 1 tabs., This record replaces record 29027954