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Advanced BWR criticality safety part Ⅱ: Cask criticality, burnup credit, sensitivity, and uncertainty analyses

机译:先进的BWR临界安全性第二部分:木桶临界度,燃耗信用,敏感性和不确定性分析

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In this study, an analysis on burnup credit for cask criticality safety in BWR spent fuel is conducted. Accurate burnup credit can be used to reduce overly conservative safety margins to increase shipping and storage efficiency while maintaining criticality level within regulatory limits. This analysis is based on advanced lattice depletion models that capture various complexities associated with BWR operation. This paper describes the second part of the two-part study which performs an out-of-core analysis of spent fuel in a transportation/storage cask. The first part of the study (Radaideh et al., 2019) developed the set of depletion models used here. In this paper, the spent fuel compositions resulting from these depletion models are used for cask criticality calculations. Uncertainty quantification of cask k(eff) is performed by combining the uncertainty in isotope inventory, nuclear data, and the statistical sampling in KENO-V.a. The uncertainty in isotopic inventory is quantified by performing a validation analysis by comparing spent fuel compositions calculated by 2D TRITON to experimentally determined spent-fuel assay data for three reactors: Fukushima Daini-2, Cooper-1, and Gundermmingen-A. The validation results demonstrate good agreement for the uranium isotopes as compared to the plutonium isotopes. Also, it was found that the uncertainty in cask k(eff) is dominated by the isotopic uncertainty and can reach about 2500 pcm, and as low as about 1700 pcm. Final results show that axial power profile, axial coolant density, control rod modeling, and the presence of gadolinium in 3D simulations have the largest effects on BWR burnup credit. This implies the need for detailed 3D modeling for accurate BWR burnup credit analysis. In addition, based on the UQ analysis considering both actinide only and actinide and fission products sets, the cask remains subcritical within 2 sigma for all depletion cases analyzed (C0-C9), even though the cask is assumed to be flooded with water and the lattices are discharged at their peak reactivity.
机译:在这项研究中,对BWR乏燃料中桶临界安全性的燃耗信用进行了分析。准确的燃耗信用可用于减少过于保守的安全边际,从而提高运输和存储效率,同时将临界水平保持在法规限制之内。该分析基于先进的晶格耗尽模型,该模型捕获了与BWR操作相关的各种复杂性。本文介绍了由两部分组成的研究的第二部分,该研究对运输/存储桶中的乏燃料进行了核心外分析。研究的第一部分(Radaideh等人,2019)开发了此处使用的耗尽模型集。在本文中,由这些耗竭模型得出的乏燃料成分用于桶临界计算。通过结合同位素清单,核数据和KENO-V.a中的统计采样中的不确定性来进行桶k(eff)的不确定性量化。通过比较2D TRITON计算出的乏燃料成分与实验确定的三个反应堆(福岛Daini-2,Cooper-1和Gundermmingen-A)的乏燃料含量,通过进行验证分析来量化同位素清单中的不确定性。验证结果表明,与the同位素相比,铀同位素具有很好的一致性。另外,还发现,桶k(eff)的不确定度主要受同位素不确定度的影响,可以达到约2500 pcm,低至约1700 pcm。最终结果表明,轴向功率曲线,轴向冷却剂密度,控制棒建模以及3D模拟中of的存在对BWR燃耗值的影响最大。这意味着需要详细的3D建模以进行准确的BWR燃耗信用分析。此外,基于仅考虑act系元素以及act系元素和裂变产物集的UQ分析,即使假定该酒桶被水和水淹没,该酒桶在所有分析的耗竭案例(C0-C9)中仍保持在2σ以内为亚临界。晶格以其峰值反应性放电。

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