A Study on the Onset of Secondary Hydriding in Defective Zr-2 Fuel for Boiling Water Reactors

Doctor Enivweru, Qingyu Wang, A. Ayodeji, Ayouba Moussa Hassane
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Abstract

One of the most common threats to the integrity of reactor fuel cladding is the geometric imperfections such as the missing pellet surface (MPS) that produces a remarkable surge in the local fuel-clad gap. The cooling water could occupy this gap leading to secondary hydriding (SH) and hydrogen embrittlement. Most studies on this subject have identified extensive radiolysis in boiling water reactors (BWRs) to be responsible for hydrogen evolution during accident conditions. However, the quantitative determination of hydrogen and how it affects zircaloy-2 during normal reactor operation has not been given adequate attention. To bridge this gap and to better predict the onset of cladding failure, this study investigates secondary hydriding and its characteristic phenomenon in a fuel cladded with zircaloy-2. Multiphysics model is used to model diffusion of heat and hydrogen, then the effect of an intermediary porous/non-protective oxide layer and the impact of dose rate from different types of radiation are studied. The contributions of the source term due to radiolysis of neutrons (n), gamma (γ), alpha (α) and beta (β) radiations are also considered. Results showed that neutrons, having a maximum dose rate of 39.9 kGy/s accounts for over 99% of ZrH precipitation in a UO2 fuel with MPS. The effect of oxide (ZrO2) thickness in SH, and the derivative of oxide thickness are also discussed.
沸水堆缺陷Zr-2燃料二次氢化发生的研究
对反应堆燃料包壳完整性最常见的威胁之一是几何缺陷,如缺失的球团表面(MPS),它会在局部燃料包壳间隙中产生显著的激增。冷却水可以占据这一空隙,导致二次氢化(SH)和氢脆。关于这一主题的大多数研究已经确定沸水反应堆(BWRs)中广泛的放射性衰变是事故条件下析氢的原因。然而,氢的定量测定及其在正常反应堆操作过程中对锆-2的影响并没有得到足够的重视。为了弥补这一空白并更好地预测包层失效的开始,本研究研究了锆合金-2包层燃料中的二次氢化及其特征现象。采用多物理场模型对热氢扩散过程进行了模拟,研究了中间多孔/非保护性氧化层的影响以及不同类型辐射剂量率的影响。源项由于中子(n)、γ (γ)、α (α)和β (β)辐射的辐射分解所作的贡献也被考虑在内。结果表明,在具有MPS的UO2燃料中,最大剂量率为39.9 kGy/s的中子占ZrH沉淀的99%以上。讨论了氧化锆(ZrO2)厚度的影响,以及氧化锆厚度的导数。
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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