Analysis of post irradiation experiments in PWR using new nuclear data libraries

Kenya Suyama, Tomohiko Iwasaki, Naohiro Hirakawa

Research output: Contribution to journalArticle

5 Citations (Scopus)

Abstract

For the precise calculation of the burnup of minor actinide isotopes, a code system-SWAT has been developed. This system analyzes burnup problems with neutron spectrum that depends on the type of a reactor and the irradiation history, using latest evaluated nuclear data files JENDL-3 or ENDF/B-VI. The post irradiation test in TRINO and the recent experiment in typical PWRs in Japan were analyzed with SWAT. These analyses show that the results of U and Pu for high burnup fuels almost agree with experimental results but those for middle burnup fuels do not agree with them. The results for Am and Cm isotopes still have large discrepancy. The average C/E of 243Am is ∼0.79, and that of 244Cm is ~0.70 for high burnup (~33,000 MWd/tU) samples. For middle burnup (~25,000 MWd/tU) samples, the C/E for 244Cm is over 2.0. The discrepancy is partially explained by considering the power peaking history of first cycle and second cycle.

Original languageEnglish
Pages (from-to)596-608
Number of pages13
Journaljournal of nuclear science and technology
Volume31
Issue number6
DOIs
Publication statusPublished - 1994 Jun

Keywords

  • Actinides
  • Burnup
  • Computer calculations
  • ENDF/B-W
  • Generation path
  • JENDL-3
  • Neutron spectra
  • Post irradiation experiments
  • Power peaking
  • SWAT

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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