Modeling and design of a separate effects irradiation test targeting fission gas release from Cr-doped UO2

IF 16.4 1区化学 Q1 CHEMISTRY, MULTIDISCIPLINARY

Accounts of Chemical Research Pub Date : 2024-09-13 DOI:10.1016/j.nucengdes.2024.113571

Jacob P. Gorton , Annabelle G. Le Coq , Zane G. Wallen , Christian M. Petrie , Joshua T. White , John T. Dunwoody , Shane Mann , Nathan A. Capps , Andrew T. Nelson

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Abstract

Fission gas release (FGR) from nuclear fuel during operation can diminish heat transfer properties across the pellet-cladding gap and increase the fuel rod internal pressure, thereby posing a concern to fuel reliability and safety during an accident. Enlarging the fuel grain size, which has been shown to improve fission gas retention, can be achieved by doping the fuel feedstock prior to sintering. In this work, the BISON fuel performance code was used to predict FGR from undoped and chromia-doped UO₂ (referred to as Cr-doped UO₂) fuel specimens with different grain sizes and across various temperatures. The BISON models identified the irradiation conditions for which FGR is most significant, and a separate effects irradiation experiment in the High Flux Isotope Reactor (HFIR) was then developed targeting those conditions. The experiment leveraged the MiniFuel irradiation capability at Oak Ridge National Laboratory and consisted of 12 fuel specimens of varying grain size and Cr content. A coupling scheme between BISON FGR results and the ANSYS finite element thermal model used for experiment design was formulated to predict cumulative FGR from each fuel specimen based on expected irradiation temperature histories. The fuel samples were fabricated and characterized as a part of this work, and the fuel compositions modeled in BISON were representative of the specimens used in the experiment. This combined modeling and experimental effort aims to study the effect of fuel grain size and Cr content on FGR and to provide simulated BISON FGR results that can be used for future model validation activities.

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针对掺杂铬的二氧化铀释放裂变气体的单独效应辐照试验的建模和设计

核燃料在运行过程中释放出的裂变气体（FGR）会降低燃料颗粒-包壳间隙的传热性能，并增加燃料棒的内部压力，从而在事故中对燃料的可靠性和安全性造成影响。扩大燃料晶粒尺寸已被证明可以改善裂变气体保留，可以通过在烧结前对燃料原料进行掺杂来实现。在这项工作中，BISON 燃料性能代码被用来预测未掺杂和掺铬二氧化铀（简称掺铬二氧化铀）燃料试样在不同晶粒尺寸和不同温度下的裂变气体保留率。BISON 模型确定了 FGR 最为显著的辐照条件，然后在高通量同位素反应堆 (HFIR) 中针对这些条件开发了单独的效应辐照实验。该实验利用了橡树岭国家实验室的迷你燃料辐照能力，包括 12 个不同晶粒大小和铬含量的燃料试样。在 BISON FGR 结果和用于实验设计的 ANSYS 有限元热模型之间制定了一个耦合方案，以根据预期的辐照温度历史预测每个燃料试样的累积 FGR。燃料样品的制作和表征是这项工作的一部分，BISON 中建模的燃料成分代表了实验中使用的样品。这项建模和实验相结合的工作旨在研究燃料粒度和铬含量对 FGR 的影响，并提供可用于未来模型验证活动的 BISON FGR 模拟结果。

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来源期刊

Accounts of Chemical Research 化学-化学综合

CiteScore

31.40

自引率

1.10%

发文量

312

审稿时长

2 months

期刊介绍： Accounts of Chemical Research presents short, concise and critical articles offering easy-to-read overviews of basic research and applications in all areas of chemistry and biochemistry. These short reviews focus on research from the author’s own laboratory and are designed to teach the reader about a research project. In addition, Accounts of Chemical Research publishes commentaries that give an informed opinion on a current research problem. Special Issues online are devoted to a single topic of unusual activity and significance. Accounts of Chemical Research replaces the traditional article abstract with an article "Conspectus." These entries synopsize the research affording the reader a closer look at the content and significance of an article. Through this provision of a more detailed description of the article contents, the Conspectus enhances the article's discoverability by search engines and the exposure for the research.