Critical experiments on low enriched uranyl nitrate solution with STACY
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
As the STACY started steady operations, systematic criticality data on low enriched uranyl nitrate solution system could be accumulated. Main experimental parameters for the cylindrical tank of 60 cm in diameter were uranium concentration and the reflector condition. Basic data on a simple geometry will be helpful for the validation of the standard criticality safety codes, and for evaluating the safety margin included in the criticality designs. Experiments on the reactivity effects of structural materials such as borated concrete and polyethylene are on schedule next year as the second series of experiments using 10 wt% enriched uranyl solution. Furthermore, neutron interacting experiments with two slab tanks will be performed to investigate the fundamental properties of neutron interaction effects between core tanks. These data will be useful for making more reasonable calculation models and for evaluating the safety margin in the criticality designs for the multiple unit system. (J.P.N.)
Files
28000204.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the first NUCEF international symposium (NUCEF'95). Engineering safety of nuclear fuel cycle facility
- Imprint Pagination
- 231 p.
- Journal Page Range
- p. 102-114.
- Report number
- JAERI-Conf--96-003
Conference
- Title
- 1. NUCEF international symposium.
- Acronym
- NUCEF'95
- Dates
- 16-17 Oct 1995.
- Place
- Hitachinaka, Ibaraki (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 28000204
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALIBRATION; CONCENTRATION RATIO; CRITICALITY; FUEL SLURRIES; MONTE CARLO METHOD; OCCUPATIONAL SAFETY; PUREX PROCESS; RADIATION PROTECTION; REACTOR CORES; REACTOR KINETICS; SAFETY ANALYSIS; SLIGHTLY ENRICHED URANIUM; URANIUM RECYCLE; URANYL NITRATES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CALCULATION METHODS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; FUEL CYCLE; FUELS; ISOTOPE ENRICHED MATERIALS; KINETICS; MATERIALS; METALS; NITRATES; NITROGEN COMPOUNDS; NUCLEAR FUELS; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTOR MATERIALS; REPROCESSING; SAFETY; SEPARATION PROCESSES; URANIUM; URANIUM COMPOUNDS; URANYL COMPOUNDS