LWR high burn-up operation and mox introduction; fuel cycle performance from the viewpoint of waste management

Yaohiro Inagaki, Tomohiko Iwasaki, Seichi Sato, Toshiaki Ohe, Kazuyuki Kato, Seishi Torikai, Yuichi Niibori, Shinya Nagasaki, Kazumi Kitayama

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1 Citation (Scopus)

Abstract

From the viewpoint of waste management, a quantitative evaluation of LWR nuclear fuel cycle system performance was carried out, considering both higher burn-up operation of UO2 fuel coupled with the introduction of MOX fuel. A major parameter to quantify this performance is the number of high-level waste (HLW) glass units generated per GWd (gigawatt-day based on reactor thermal power generation before electrical conversion). This parameter was evaluated for each system up to a maximum burn-up of 70GWd/THM (gigawatt-day per ton of heavy metal) assuming current conventional reprocessing and vitrification conditions where the waste loading of glass is restricted by the heat generation rate, the MoO3 content, or the noble metal content. The results showed that higher burn-up operation has no significant influence on the number of glass units generated per GWd for UO2 fuel, though the number of glass units per THM increases linearly with burn-up and is restricted by the heat generation rate. On the other hand, the introduction of MOX fuel causes the number of glass units per GWd to double owing to the increase in the heat generation rate. An extended cooling period of the spent fuel prior to reprocessing effectively reduces the heat generation rate for UO2 fuel, while a separation of minor actinides (Np, Am, and Cm) from the high-level waste provides additional reduction for MOX fuel. However, neither of these leads to a substantial reduction in the number of glass units, since the MoO3 content or the noble metal content restricts the number of glass units rather than the heat generation rate. These results suggest that both the MoO3 content and the noble metal content provide the key to reducing the amount of waste glass that is generated, leading to an overall improvement in fuel cycle system performance.

Original languageEnglish
Pages (from-to)677-689
Number of pages13
Journaljournal of nuclear science and technology
Volume46
Issue number7
DOIs
Publication statusPublished - Jul 2009

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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