Non-Destructive Gamma-Ray Spectrometry on Spent Fuels of a Boiling Water Reactor

The spent fuels from the JPDR-I reactor were measured by means of a γ-scanning facility installed in the fuel storage pool. The spatial distributions of the fission products ( 134 Cs and 137 Cs) were measured and analyzed in reference to the effects of control rod pattern. The ratios holding between...

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Published inJournal of nuclear science and technology Vol. 12; no. 1; pp. 24 - 34
Main Authors MATSUURA, Shojiro, TSURUTA, Harumichi, SUZAKI, Takenori, OKASHITA, Hiroshi, UMEZAWA, Hirokazu, NATSUME, Haruo
Format Journal Article
LanguageEnglish
Published Tokyo Taylor & Francis Group 01.01.1975
Taylor & Francis Ltd
Subjects
burnup
BWR type reactors
cesium 134
cesium 137
fission products
gamma fuel scanning
gamma spectrometry
JPDR reactor
Li-drifted Ge detectors
non-destructive testing
spatial distribution
spent fuels
uranium dioxide
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Summary:The spent fuels from the JPDR-I reactor were measured by means of a γ-scanning facility installed in the fuel storage pool. The spatial distributions of the fission products ( 134 Cs and 137 Cs) were measured and analyzed in reference to the effects of control rod pattern. The ratios holding between the products of neutron capture and of direct fission ( 134 Cs/ 137 Cs and 154 Eu/ 137 Cs) were also examined for its relevance to non-destructive burnup determination. The activity ratios of the fission products can be expressed by a linear function of burnup, provided that corrections are made to account for differences in irradiation history and for spatial variations in the neutron spectrum.
ISSN:0022-3131
1881-1248
DOI:10.1080/18811248.1975.9733065