It is very useful for fuel integrity evaluation to accumulate knowledge base on fuel behavior of uranium and plutonium mixed oxide (MOX) fuel used in light water reactors (LWRs). Fission gas release is one of fuel behaviors which have an impact on fuel integrity evaluation. Fission gas release behavior of MOX fuels having heterogeneous structure is focused in this study. A concerned linear heat rate (LHR) for fission gas release is introduced by MOX fuel irradiation test in BR-2 reactor. The concerned LHR is defined in this paper to be the LHR at which a certain additional fission gas release thermally occurs. In addition, it is found that fission gas atoms exist in the fuel matrix simultaneously in the fission gas bubbles. The corresponding amounts are also clarified. Such kind of technical information is needed to better understand fuel behavior during not only normal operation, but also accident like reactivity initiated accident (RIA).
|Title of host publication||Proceedings of Fontevraud 8: Contribution of Materials Investigations and Operating Experience to LWRs’ Safety, Performance and Reliability|
|Place of Publication||France|
|State||Published - Sep 2014|
|Event||2014 - FONTEVRAUD 8 : Contribution of Materials Investigations and Operating Experience to Light Water NPPs’ Safety, Performance and Reliability - SFEN - Sociéte Francaise d' Energie Nucléaire, Avignon|
Duration: 15 Sep 2014 → 18 Sep 2014
|Conference||2014 - FONTEVRAUD 8|
|Period||2014-09-15 → 2014-09-18|