The behavior of advanced gas reactor simulated spent nuclear fuels in wet interim storage conditions

E. Howett, C. Boxall, Richard J. Wilbraham, D. Hambley
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引用次数: 3

Abstract

The safe interim storage of spent nuclear fuel is important to prevent the degradation of the containers and fuel rods – both fuel pellets and cladding – thus avoiding the release of radiation and allowing the fuel to be safely handled on transfer to a long term disposal facility. The corrosion of pure UO2 and UK Advanced Gas-cooled Reactor (AGR) simulated spent nuclear fuels (SIMFUELs) was studied under conditions typical of those found in interim spent fuel storage pond waters. With respect to the dissolution of spent fuel, it appears to be advantageous to dose the ponds to pH≈11.4. The alkaline conditions in the pond water suppress the dissolution as UO2 which may otherwise occur at neutrality and lower pHs.
先进气体反应堆模拟了乏燃料在湿过渡贮存条件下的行为
乏核燃料的安全临时储存对于防止容器和燃料棒(包括燃料球团和包层)的降解非常重要,从而避免辐射的释放,并允许燃料在转移到长期处置设施时得到安全处理。研究了纯UO2和英国先进气冷堆(AGR)模拟乏燃料(SIMFUELs)在乏燃料临时贮存池中典型的腐蚀条件下的腐蚀。关于乏燃料的溶解,将池的pH值加到≈11.4似乎是有利的。池塘水中的碱性条件抑制了UO2的溶解,否则在中性和低ph值时可能会发生UO2的溶解。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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