論文

査読有り
1995年3月

Determination of the modified conversion ratio of light-water-moderated uranium-plutonium mixed-oxide-fuel lattice

Nuclear Science and Engineering
  • Ken Nakajima
  • ,
  • Masanori Akai
  • ,
  • Takenori Suzaki

119
3
開始ページ
175
終了ページ
181
記述言語
英語
掲載種別
研究論文(学術雑誌)
DOI
10.13182/NSE95-A24083
出版者・発行元
AMER NUCLEAR SOCIETY

The modified conversion ratio (MCR) (the ratio of the 238U capture rate to the total fission rate) in a light-water-moderated uranium-plutonium mixed-oxide- (MOX-) fuel lattice was measured for four types of lattices with different plutonium enrichment. In the current method, the relative reaction rates of 238U capture and total fission were obtained from nondestructive gamma-ray spectrometry of 239Np and fission products, respectively, which accumulated in the fuel rod irradiated at the Tank-Type Critical Assembly. The measured results of the fission rates derived from two different fission products agreed well with each other, and the measured MCRs showed good agreement with the results of the Monte Carlo calculation with the whole-core model. Therefore, the current nondestructive method is applicable to the MCR measurement of MOX fuel.

リンク情報
DOI
https://doi.org/10.13182/NSE95-A24083
Web of Science
https://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=JSTA_CEL&SrcApp=J_Gate_JST&DestLinkType=FullRecord&KeyUT=WOS:A1995QL47900003&DestApp=WOS_CPL
URL
http://www.scopus.com/inward/record.url?eid=2-s2.0-0029276429&partnerID=MN8TOARS
Scopus Citedby
https://www.scopus.com/inward/citedby.uri?partnerID=HzOxMe3b&scp=0029276429&origin=inward
ID情報
  • DOI : 10.13182/NSE95-A24083
  • ISSN : 0029-5639
  • ORCIDのPut Code : 45946806
  • SCOPUS ID : 0029276429
  • Web of Science ID : WOS:A1995QL47900003

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