Volatile fission product behaviour during thermal annealing of irradiated UO2 fuel oxidised up to U3O8
Volatile fission product behaviour during thermal annealing of irradiated UO2 fuel oxidised up to U3O8
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DOI：
10.1016/j.jnucmat.2007.03.174
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发表时间：
2008-01-31
影响因子：
3.1
通讯作者：
Rondinella, V. V.
中科院分区：
文献类型：
--
作者：
Hiernaut, J. -P.;Wiss, T.;Rondinella, V. V.
本文研究了辐照过的二氧化铀样品在高温退火过程中裂变产物的行为和释放与氧化态的关系。将预氧化为八氧化三铀的样品的行为与来自相同芯块径向位置的未经预处理的燃料的行为进行比较。克努森细胞质谱仪技术被用于高达1900 K的预氧化的样品和高达2800 K的未处理的样品。这两种测试都是在真空中进行的。根据释放曲线和微探针分析，估计了不同裂变产物在体相和气相中的可能化学形态。这项研究主要涉及碘，碲，铯，铷，锶，钡，锝和钼，其渗出行为受到预氧化处理的强烈影响，导致在1900 K时几乎完全释放。在>1900 K的温度下观察到锆、镧系元素和锕系元素的释放，这仅在未经预处理的二氧化铀实验的情况下达到。(C)2007 Elsevier B.V.保留所有权利。
The behaviour and release of fission products during high-temperature annealing of irradiated UO2 samples have been studied as a function of the oxidation state. The behaviour of a sample pre-oxidised to U3O8 was compared to that of non-pre-treated fuel from the same pellet radial location. The Knudsen cell mass spectrometer technique was used up to 1900 K for the pre-oxidised sample and up to 2800 K for the untreated sample. Both types of tests were run in vacuum. The possible chemical forms of the different fission products in the bulk and in the vapour phase have been estimated from the release curves and microprobe analysis. This study concerns essentially iodine, tellurium, caesium, rubidium, strontium, barium, technetium and molybdenum, whose effusion behaviour was strongly affected by the pre-oxidation treatment, resulting in an almost complete release by 1900 K. Release of zirconium, the lanthanides and actinides was observed at temperatures >1900 K, reached only in the case of the non-pre-treated UO2 experiments. (C) 2007 Elsevier B.V. All rights reserved.