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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Rapid aqueous release of fission products from high burn-up LWR fuel: Experimental results and correlations with fission gas release
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Rapid aqueous release of fission products from high burn-up LWR fuel: Experimental results and correlations with fission gas release

机译:从高燃耗轻水堆燃料中快速释放裂变产物的水:实验结果及其与裂变气体释放的关系

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Studies of the rapid aqueous release of fission products from UO _2 and MOX fuel are of interest for the assessment of the safety of geological disposal of spent fuel, because of the associated potential contribution to dose in radiological safety assessment. Studies have shown that correlations between fission gas release (FGR) and the fraction rapidly leached of various long-lived fission products can provide a useful method to obtain some of this information. Previously, these studies have been limited largely to fuel with burn-up values below 50 MWd/kg U. Collaborative studies involving SKB, Studsvik, Nagra and PSI have provided new data on short-term release of ~(137)Cs and ~(129)I for a number of fuels irradiated to burn-ups of 50-75 MWd/kgU. In addition a method for analysis of leaching solutions for ~(79)Se was developed. The results of the studies show that the fractional release of ~(137)Cs is usually much lower than the FGR covering the entire range of burn-ups studied. Fractional ~(129)I releases are somewhat larger, but only in cases in which the fuel was forcibly extracted from the cladding. Despite the expected high degree of segregation of fission gas (and by association ~(137)Cs and ~(129)I) in the high burn-up rim, no evidence was found for a significant contribution to release from the rim region. The method for ~(79)Se analysis developed did not permit its detection. Nonetheless, based on the detection limit, the results suggest that ~(79)Se is not preferentially leached from spent fuel.
机译:UO _2和MOX燃料中裂变产物的快速水释放研究对于评估乏燃料的地质处置安全性是有意义的,因为在放射安全性评估中可能对剂量有潜在的贡献。研究表明,裂变气体释放(FGR)与各种长寿命裂变产物迅速浸出的馏分之间的相关性可以为获得某些此类信息提供有用的方法。以前,这些研究主要限于燃耗值低于50 MWd / kg U的燃料。涉及SKB,Studsvik,Nagra和PSI的合作研究提供了〜(137)Cs和〜( 129)I表示照射到燃尽的燃料数量为50-75 MWd / kgU。此外,还开发了一种分析〜(79)Se浸出溶液的方法。研究结果表明,〜(137)Cs的分数释放通常比覆盖整个研究燃耗范围的FGR低得多。 〜(129)I的分数释放稍大,但仅在强制从包层中抽取燃料的情况下。尽管在高燃烧边缘中裂变气体的偏析程度很高(并伴有〜(137)Cs和〜(129)I的缔合),但没有发现对从边缘区域释放的重大贡献的证据。开发的〜(79)Se分析方法不允许对其进行检测。然而,基于检测极限,结果表明〜(79)Se并非优先从乏燃料中浸出。

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