颗粒
裂变材料
乏核燃料
核工程
乏燃料池
裂变产物
混合氧化物燃料
材料科学
废物管理
制作
核燃料
燃料元件故障
弹丸
环境科学
放射化学
核化学
冶金
铀
化学
工程类
核物理学
复合材料
中子
物理
医学
替代医学
病理
作者
Jungwon Lee,Geun-Il Park,Yong Seok Choi
标识
DOI:10.1080/00223131.2012.730898
摘要
Technology for the direct usage of a spent PWR fuel in CANDU reactors (DUPIC) was developed in KAERI to reduce the amount of spent fuel. DUPIC fuel pellets were fabricated using a dry processing method to re-fabricate CANDU fuel from spent PWR fuel without any intentional separation of fissile materials or fission products. The DUPIC fuel element fabrication process satisfied a quality assurance program in accordance with the Canadian standard. For the DUPIC fuels with various fuel burn-ups between 27,300 and 65,000 MWd/tU, the sintered pellet density decreased with increasing fuel burn-ups. Fission gas releases and powder properties of the spent fuel also influenced the DUPIC fuel characteristics. Measurement of cesium content released from green pellets revealed that their sintered density significantly depended on sintering temperature history. It was useful to establish a DUPIC fuel fabrication technology in which a high-burn-up fuel with 65,000 MWd/tU was treated.
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