Nuclear Design Study on a Super High-burnup Fuel Assembly for Pressurized Water Reactors Using Transuranium

この論文にアクセスする

この論文をさがす

著者

抄録

A conceptual design study was carried out on a super high-burnup mixed-oxide (MOX) fuel assembly(SHB FA) for pressurized water reactors (PWRs) using transuranium (TRU). This study aims to avoid the surplus plutonium (Pu) accumulation and to reduce the accumulation of long-lived radioactive minor actinides (MAs) by utilizing the currently existing PWRs under the condition that the Japanese program to develop fast breeder reactors (FBRs) is tend to delay. For this purpose, an SHB FA with discharged burnup of -80GWd/t was investigated by utilizing MAs positively as both burnable absorbers and fissile suppliers and loading high-content Pu. It is possible to load the SHB FAs in a current PWR together with UO<SUB>2</SUB> FAs and to use 2.5 times as much amount of Pu as that in a standard 1/3 MOX core. Moreover, it is found to be possible to reduce the total number of fresh FAs further from that of a high-burnup (55GWd/t in maximum)UO<SUB>2</SUB> (4.9wt%) core and also to reduce the accumulation of MAs in the nuclear fuel cycle significantly.

収録刊行物

  • Journal of nuclear science and technology  

    Journal of nuclear science and technology 34(7), 644-654, 1997-07-25 

    Atomic Energy Society of Japan

参考文献:  7件

参考文献を見るにはログインが必要です。ユーザIDをお持ちでない方は新規登録してください。

被引用文献:  1件

被引用文献を見るにはログインが必要です。ユーザIDをお持ちでない方は新規登録してください。

各種コード

  • NII論文ID(NAID)
    10002077491
  • NII書誌ID(NCID)
    AA00703720
  • 本文言語コード
    ENG
  • 資料種別
    ART
  • ISSN
    00223131
  • NDL 記事登録ID
    4260273
  • NDL 雑誌分類
    ZM35(科学技術--物理学)
  • NDL 請求記号
    Z53-A460
  • データ提供元
    CJP書誌  CJP引用  NDL  J-STAGE 
ページトップへ