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CRITICALITY SAFETY ANALYSIS OF AS-LOADED SPENT NUCLEAR FUEL CASKS

机译:装料核燃料瓶的临界安全性分析

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The final safety analysis report (FSAR) or the safety analysis report (SAR) for a particular spent nuclear fuel (SNF) cask (both bare fuel and canister-based) system documents models and calculations used to demonstrate that a system meets the regulatory requirements under all normal, off-normal, and accident conditions of spent fuel storage, as well as the normal and accident conditions of transportation. FSAR/SAR calculations and approved content specifications are intended to be bounding in nature to certify cask systems for a variety of fuel characteristics with simplified SNF loading requirements. Therefore, in general, loaded cask systems possess excess and uncredited criticality margins (i.e., the difference between the licensing basis and the as-loaded calculations). This uncredited margin could be quantified by (1) employing more detailed cask-specific evaluations that credit the actual as-loaded cask inventory and (2) taking into account full (actinide and fission product) burnup credit. This uncredited criticality margin could be used to offset uncertainties in the safety basis to account for the effects of system aging during extended dry storage prior to transportation. Additionally, the uncredited criticality margin could also potentially be credited to offset increases in SNF system reactivity that may occur over a repository performance period (e.g., 10,000 years or more) as the system undergoes degradation and internal geometry changes. This paper summarizes an assessment of cask-specific as-loaded criticality margins for 215 loaded casks of SNF stored at eight reactor sites under fully flooded conditions to assess the margins available during transportation after extended storage. It is observed that the calculated k_(eff) margin varies from 0.05 to almost 0.3 Δk_(eff) for the eight selected reactor sites, demonstrating that significant uncredited safety margins are present. In addition, this paper evaluates the sufficiency of this excess margin in applications involving direct disposal of currently loaded SNF canisters (for canister-based systems) in a repository.
机译:最终安全分析报告(FSAR)或特定乏核燃料(SNF)桶(基于裸燃料和罐的基础)系统的安全分析报告(SAR)模型和计算,用于证明系统符合法规要求在所有正常,异常和意外情况下,乏燃料存储,以及运输的正常和意外情况下。 FSAR / SAR计算和批准的内容规格旨在对具有简化SNF装载要求的各种燃料特性的桶系统进行认证,本质上是有约束力的。因此,总的来说,已装载的木桶系统具有过高的和未经信用的临界边际(即许可基础与已装载计算之间的差异)。可以通过(1)使用更详细的特定于酒桶的评估来对实际的酒桶存货进行贷记,以及(2)考虑完整的(act系元素和裂变产物)燃尽信用来量化此未计入的保证金。这种未经信用的临界裕度可用于抵消安全基础中的不确定性,以解决运输之前延长的干燥存储期间系统老化的影响。另外,未信用的临界裕度也可能被认为是抵消了随着系统经历退化和内部几何形状变化而可能在存储库性能期间(例如,10,000年或更长时间)内发生的SNF系统反应性的增加。本文总结了对在完全淹没条件下存储在八个反应堆地点的215个SNF装载桶的特定于装箱的临界临界裕度的评估,以评估长期储存后在运输过程中可用的裕度。可以看出,对于八个选定的反应堆站点,计算得出的k_(eff)裕度从0.05到几乎0.3Δk_(eff)变化,这表明存在大量未记入的安全裕度。此外,本文还评估了在涉及直接处置存储库中当前装载的SNF容器(用于基于容器的系统)的应用程序中,该多余边际的充分性。

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