Corrections to the 148Nd method of evaluation of burnup for the PIE samples from Mihama-3 and Genkai-1 reactors
Creators
- 1. Fuel Cycle Facility Safety Research Group, Nuclear Safety Research Center, Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki 319-1195 (Japan)
- 2. Japan Research Institute, Limited, 16 Ichiban-cho, Chiyoda-ku, Tokyo 102-0082 (Japan)
Description
The value of the burnup is one of the most important parameters of samples taken by post-irradiation examination (PIE). Generally, it is evaluated by the Neodymium-148 method. Precise evaluation of the burnup value requires: (1) an effective fission yield of 148Nd; (2) neutron capture reactions of 147Nd and 148Nd; (3) a conversion factor from fissions per initial heavy metal to the burnup unit GWd/t. In this study, the burnup values of the PIE data from Mihama-3 and Genkai-1 PWRs, which were taken by the Japan Atomic Energy Research Institute, were re-evaluated using more accurate corrections for each of these three items. The PIE data were then re-analyzed using SWAT and SWAT2 code systems with JENDL-3.3 library. The re-evaluation of the effective fission yield of 148Nd has an effect of 1.5-2.0% on burnup values. Considering the neutron capture reactions of 147Nd and 148Nd removes dependence of C/E values of 148Nd on the burnup value. The conversion factor from FIMA(%) to GWd/t changes according to the burnup value. Its effect on the burnup evaluation is small for samples having burnup of larger than 30 GWd/t. The analyses using the corrected burnup values showed that the calculated 148Nd concentrations and the PIE data is approximately 1%, whereas this was 3-5% in prior analyses. This analysis indicates that the burnup values of samples from Mihama-3 and Genkai-1 PWRs should be corrected by 2-3%. The effect of re-evaluation of the burnup value on the neutron multiplication factor is an approximately 0.6% change in PIE samples having the burnup of larger than 30 GWd/t. Finally, comparison between calculation results using a single pin-cell model and an assembly model is carried out. Because the results agreed with each other within a few percent, we concluded that the single pin-cell model is suitable for the analysis of PIE samples and that the underestimation of plutonium isotopes, which occurred in the previous analyses, does not result from a geometry model
Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2005.11.009;
- PII
- S0306-4549(05)00273-2;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 33
- Journal Issue
- 4
- Journal Page Range
- p. 335-342
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37071606
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP; CAPTURE; COMPARATIVE EVALUATIONS; CORRECTIONS; FISSION YIELD; GENKAI-1 REACTOR; JAERI; MIHAMA-3 REACTOR; MULTIPLICATION FACTORS; NEODYMIUM 147; NEODYMIUM 148; NEUTRON REACTIONS; NUCLEAR DATA COLLECTIONS; PLUTONIUM ISOTOPES; POST-IRRADIATION EXAMINATION; S CODES
- Descriptors DEC
- BARYON REACTIONS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; COMPUTER CODES; DAYS LIVING RADIOISOTOPES; DIMENSIONLESS NUMBERS; ENRICHED URANIUM REACTORS; EVALUATION; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; HADRON REACTIONS; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOTOPES; JAPANESE ORGANIZATIONS; NATIONAL ORGANIZATIONS; NEODYMIUM ISOTOPES; NUCLEAR REACTION YIELD; NUCLEAR REACTIONS; NUCLEI; NUCLEON REACTIONS; POWER REACTORS; PWR TYPE REACTORS; RADIOISOTOPES; RARE EARTH NUCLEI; REACTORS; STABLE ISOTOPES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; YIELDS
Optional Information
- Copyright
- Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.