Technical development on burn-up credit for spent LWR fuels
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
Technical development on burn-up credit for spent LWR fuels had been performed at JAERI since 1990 under the contract with Science and Technology Agency of Japan entitled 'Technical Development on Criticality Safety Management for Spent LWR Fuels'. Main purposes of this work are to obtain the experimental data on criticality properties and isotopic compositions of spent LWR fuels and to verify burn-up and criticality calculation codes. In this work three major experiments of exponential experiments for spent fuel assemblies to obtain criticality data, non-destructive gamma-ray measurement of spent fuel rods for evaluating axial burn-up profiles, and destructive analyses of spent fuel samples for determining precise burn-up and isotopic compositions were carried out. The measured data obtained were used for validating calculation codes as well as an examination of criticality safety analyses. Details of the work are described in this report. (author)
Availability note (English)
Available from INIS in electronic formFiles
32011832.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 392 p.
- Report number
- JAERI-Tech--2000-071
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 32011832
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; COMPUTER CODES; CRITICALITY; GAMMA FUEL SCANNING; PWR TYPE REACTORS; RADIATION ACCIDENTS; RADIOCHEMICAL ANALYSIS; SAFETY; SPENT FUEL STORAGE; SPENT FUELS; STORAGE FACILITIES; VALIDATION
- Descriptors DEC
- ACCIDENTS; CHEMICAL ANALYSIS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EVALUATION; FUEL SCANNING; FUELS; GAMMA RADIOGRAPHY; INDUSTRIAL RADIOGRAPHY; MATERIALS; MATERIALS TESTING; NONDESTRUCTIVE TESTING; NUCLEAR FUELS; POWER REACTORS; QUANTITATIVE CHEMICAL ANALYSIS; REACTOR MATERIALS; REACTORS; STORAGE; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 41 refs., 143 figs., 178 tabs.