Burning of MOX fuels in LWRs; Fuel history effects on thermal properties of hull and end piece wastes and the repository performance

Fumio Hirano, Seichi Sato, Tamotsu Kozaki, Yaohiro Inagaki, Tomohiko Iwasaki, Toshiaki Ohe, Kazuyuki Kato, Kazumi Kitayama, Shinya Nagasaki, Yuichi Niibori

Research output: Contribution to journalArticle

Abstract

The thermal impacts of hull and end piece wastes from the reprocessing of MOX spent fuels burned in LWRs on repository performance were investigated. The heat generation rates in MOX spent fuels and the resulting heat generation rates in hull and end piece wastes change depending on the history of MOX fuels. This history includes the burn-up of UO 2 spent fuels from which the Pu is obtained, the cooling period before reprocessing, the storage period of fresh MOX fuels before being loaded into an LWR, as well as the burn-up of the MOX fuels. The heat generation rates in hull and end piece wastes from the reprocessing of MOX spent fuels with any of those histories are significantly larger than those from UO 2 spent fuels with burn-ups of 45 GWd/THM. If a temperature below 808C is specified for cement-based materials used in waste packages after disposal, the allowable number of canisters containing compacted hull and end pieces in a package for 45 and 70 GWd-MOX needs to be limited to a value of 0.4-1.6, which is significantly lower than 4.0 for 45 GWd-UO 2.

Original languageEnglish
Pages (from-to)310-319
Number of pages10
Journaljournal of nuclear science and technology
Volume49
Issue number3
DOIs
Publication statusPublished - 2012 Apr 5

Keywords

  • Burn-up
  • Cementitious material
  • Cooling period
  • Geological disposal
  • History of MOX fuels
  • Hull and end piece waste
  • MOX-LWR
  • Thermal impact

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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