Effects of interaction between molten zircaloy and irradiated MOX fuel on the fission product release behavior
Effects of interaction between molten zircaloy and irradiated MOX fuel on the fission product release behavior
复制标题
熔融锆合金与辐照MOX燃料之间的相互作用对裂变产物释放行为的影响
DOI：
10.1080/00223131.2014.896229
复制
发表时间：
2014
影响因子：
1.2
通讯作者：
S. Koyama
中科院分区：
文献类型：
--
作者：
Kosuke Tanaka;S. Miwa;I. Sato;T. Hirosawa;Shinobu Sekine;M. Osaka;H. Obayashi;S. Koyama
作为获得高温化学相互作用对裂变产物释放行为影响的实验数据的第一步，我们重点研究了辐照后的铀钚混合氧化物(MOX)燃料在熔融锆合金(Zry)中的溶解，并在还原气氛下进行了加热试验。对辐照后的MOX燃料芯块和包壳在2373K下进行了5分钟的加热试验。在试验过程中监测了铯(特别是137Cs)的部分释放速率，并对其释放行为进行了评估。并对加热后的样品进行了显微组织观察和元素分布测量。我们通过实验证明，熔融Zry的燃料溶解加速了燃料颗粒中Cs的释放。
As a first step for obtaining experimental data on the effects of high-temperature chemical interaction on fission product release behavior, we focused on the dissolution of irradiated uranium plutonium mixed oxide (MOX) fuel by molten zircaloy (Zry) and carried out a heating test under the reducing atmosphere. Pieces of an irradiated MOX fuel pellet and cladding were subjected to the heating test at 2373 K for five minutes. The fractional release rate of cesium (specifically 137Cs) was monitored during the test and its release behavior was evaluated. The observation of microstructures and measurements of elemental distribution in the heated specimen were also performed. We demonstrated experimentally that the fuel dissolution by molten Zry accelerated the release of Cs from the fuel pellets.