Modelling of fine fragmentation and fission gas release of UO2 fuel in accident conditions

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY EPJ Nuclear Sciences & Technologies Pub Date : 2019-09-01 DOI:10.1051/epjn/2019030
L. Jernkvist
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引用次数: 10

Abstract

In reactor accidents that involve rapid overheating of oxide fuel, overpressurization of gas-filled bubbles and pores may lead to rupture of these cavities, fine fragmentation of the fuel material, and burst-type release of the cavity gas. Analytical rupture criteria for various types of cavities exist, but application of these criteria requires that microstructural characteristics of the fuel, such as cavity size, shape and number density, are known together with the gas content of the cavities. In this paper, we integrate rupture criteria for two kinds of cavities with models that calculate the aforementioned parameters in UO2 LWR fuel for a given operating history. The models are intended for implementation in engineering type computer programs for thermal-mechanical analyses of LWR fuel rods. Here, they have been implemented in the FRAPCON and FRAPTRAN programs and validated against experiments that simulate LOCA and RIA conditions. The capabilities and shortcomings of the proposed models are discussed in light of selected results from this validation. Calculated results suggest that the extent of fuel fragmentation and transient fission gas release depends strongly on the pre-accident fuel microstructure and fission gas distribution, but also on rapid changes in the external pressure exerted on the fuel pellets during the accident.
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事故条件下UO2燃料精细碎裂和裂变气体释放的建模
在涉及氧化物燃料快速过热的反应堆事故中,充满气体的气泡和孔隙的过压可能导致这些空腔破裂,燃料材料的细碎裂,以及空腔气体的爆裂型释放。存在各种类型空腔的分析破裂准则,但这些准则的应用需要知道燃料的微观结构特征,如空腔的大小、形状和数量密度,以及空腔的气体含量。在本文中,我们将两种空腔的破裂准则与计算给定运行历史下UO2轻水堆燃料上述参数的模型相结合。这些模型的目的是在工程型计算机程序中实现对轻水堆燃料棒的热-力学分析。在这里,它们已经在FRAPCON和FRAPTRAN程序中实现,并针对模拟LOCA和RIA条件的实验进行了验证。根据本次验证的选定结果,讨论了所提出模型的能力和缺点。计算结果表明,燃料碎裂和瞬态裂变气体释放的程度在很大程度上取决于事故前燃料微观结构和裂变气体分布,但也取决于事故期间施加在燃料球团上的外部压力的快速变化。
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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来源期刊
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
20.00%
发文量
18
审稿时长
10 weeks
期刊最新文献
Technical note: stable and unstable reactors Templates of expected measurement uncertainties for neutron-induced capture and charged-particle production cross section observables Templates of expected measurement uncertainties for (n, xn) cross sections Templates of expected measurement uncertainties for total neutron cross-section observables Templates of expected measurement uncertainties for prompt fission neutron spectra
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