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首页> 外文期刊>Annals of nuclear energy >Criticality and uncertainty assessment of assembly misloading in BWR transportation cask
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Criticality and uncertainty assessment of assembly misloading in BWR transportation cask

机译:BWR运输桶中组件卸载的危险性和不确定性评估

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摘要

Misloading of a spent fuel assembly could occur during the loading process of transportation casks due to inaccurate burnup records or mistaken assembly identification. Therefore, criticality safety analysis is important for such conditions to ensure that the cask remains subcritical with a sufficient margin. Investigations of assembly misload in PWR spent fuel cask has been conducted in previous studies, a similar analysis is still needed for BWR casks because of the differences between them, such as operational conditions, assembly size, gadolinium rods presence, enrichment variation, and others. Consequently, a quantitative computational criticality safety analysis is conducted in this work for a variety of misloading conditions in a BWR burnup credit shipping cask (GBC-68). The uncertainty in k(eff) estimation due to both nuclear data and statistical sampling has been quantified to ensure that keff uncertainty margin is within criticality bounds. The analysis has been carried out using different modules within the SCALE code system, namely, TRITON, KENO-V.a, and TSUNAMI-3D. The results demonstrate that BWR misloading has different trend than PWR because of the presence of gadolinium rods. Two sets of nuclides have been considered in this analysis to show the credit of the fission products: major actinides and major actinides plus fission products. The peak reactivity burnup is calculated to be 24 GWD/MTU. Assembly misload results illustrate that misloaded assemblies with burnup less than the peak reactivity burnup insert more reactivity than the fresh misloaded assemblies, which is the opposite for PWR where misloaded fresh assemblies insert more reactivity than the burned assemblies. The uncertainty analysis demonstrates that reactivity uncertainty is within 5% for most of the cases considered in this analysis. The estimation of probability of occurrence of misloading accidents is out of scope of this work and it is left as a future work. Published by Elsevier Ltd.
机译:由于不正确的燃尽记录或错误的组件标识,在运输桶的装载过程中可能会发生乏燃料组件的错误装载。因此,临界安全性分析对于此类条件非常重要,以确保容器保持足够的裕度处于亚临界状态。在以前的研究中已经对压水堆乏燃料桶中的组装失载进行了研究,由于BWR桶之间的差异,例如操作条件,组装尺寸,g棒的存在,浓缩变化等,仍需要进行类似的分析。因此,这项工作针对BWR燃耗信用运输桶(GBC-68)中的各种误载情况进行了定量计算的临界安全性分析。已经量化了由于核数据和统计采样而导致的k(eff)估计的不确定性,以确保keff不确定性裕度在临界范围内。使用SCALE代码系统中的不同模块TRITON,KENO-V.a和TSUNAMI-3D进行了分析。结果表明,由于WR棒的存在,BWR的卸荷趋势与PWR有所不同。在此分析中考虑了两套核素,以显示裂变产物的功劳:主要的act系元素和主要的in系元素加上裂变产物。计算出的反应性峰值消耗为24 GWD / MTU。组件不载结果表明,燃耗小于峰值反应性的失载组件燃耗比新鲜的不载组件要高,而PWR则相反,不载重的新鲜组件要比烧成组件具有更高的反应性。不确定性分析表明,在此分析中考虑的大多数情况下,反应性不确定性均在5%以内。误装事故发生概率的估计超出了这项工作的范围,将留作未来的工作。由Elsevier Ltd.发布

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