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AXIAL BURNUP PROFILE INFLUENCE ON CRITICALITY SAFETY OF WWER SPENT FUEL

机译:轴向爆破轮廓对WWER燃料燃料临界安全性的影响

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Criticality safety assessment for WWER-440 NUHOMS~® cask with spent nuclear fuel from Armenian NPP has been performed. The cask was designed in a such way that the neutron multiplication factor k_(eff) must be below 0,95 for all operational modes and accident conditions. Usually for criticality analysis, fresh fuel approach with the highest enrichment is taken as conservative assumption as it was done for ANPP. Nuclear and Radiation Safety Centre of Armenian Nuclear Regulatory Authority (NRSC ANRA) in order to improve future fuel storage efficiency, initiated research with taking into account burn up credit in the criticality safety assessment.rnAxial burn up profile (end effect) has essential impact on criticality safety justification analysis. However this phenomenon wasn't taken into account in the Safety Analysis Report of NUHOMS~® spent fuel storage constructed on the site of ANPP. Although ANRA doesn't yet accept burn up credit approach for ANPP spent fuel storage, assessment of impact of axial burn up profile on criticality of spent fuel assemblies has important value for future activities of ANRA.rnThis paper presents results of criticality safety analysis of spent fuel assemblies with axial burn up profile. Horizontal burn up profile isn't taken account since influence of the horizontal variation of the burn up is much less than the axial variation. The Actinides and Actinides + Fission Products approach are discussed. The calculations were carried out with STARBUCS module of SCALE 5.0 code package developed at Oak Ridge National laboratory. SCALE5.0 sequence CSAS26 (KENO-VI) was used for evaluation the k_(eff) for 3-D problems. Obtained results showed that criticality of ANPP spent fuel cask is very sensitive to the end effect. Using Burn up profilesrnof Control Assemblies in both approaches leads to much more increasing than in case of Working Assemblies. Usually increasing burn up leads to decreasing △k_(eff), hence decreasing end effect. However for WWER-440 Control Assemblies that worked only within 6th (operative) group increasing burn up leads to increasing of the end effect.
机译:已对来自亚美尼亚核电厂的乏核燃料的WWER-440 NUHOMS〜®桶进行了临界安全评估。桶的设计方式是,对于所有运行模式和事故情况,中子倍增系数k_(eff)必须低于0.95。通常,对于临界分析,采用最高浓缩的新鲜燃料方法作为对ANPP所做的保守假设。亚美尼亚核监管局(NRSC ANRA)核与辐射安全中心(NRSC ANRA)为了提高未来的燃料存储效率,在关键安全性评估中考虑到了燃尽量而开始了研究。轴向燃尽特性(最终影响)对临界安全性理由分析。但是,在ANPP现场建造的NUHOMS〜®乏燃料存储的《安全分析报告》中并未考虑到这种现象。尽管ANRA尚未接受ANPP乏燃料存储的燃耗信用方法,但评估轴向燃尽轮廓对乏燃料组件的临界性的影响对于ANRA的未来活动具有重要价值。rn本文介绍了乏燃料临界安全性分析的结果轴向燃烧轮廓的燃油组件。由于燃烧的水平变化的影响远小于轴向变化,因此未考虑水平燃烧轮廓。讨论了in系元素和Act系元素+裂变产物方法。计算是使用Oak Ridge国家实验室开发的SCALE 5.0代码包的STARBUCS模块进行的。 SCALE5.0序列CSAS26(KENO-VI)用于评估3-D问题的k_(eff)。获得的结果表明,ANPP乏燃料桶的临界度对最终效果非常敏感。与工作组件相比,在两种方法中都使用Burn up profilernof控制组件会带来更多的增长。通常,增加燃耗会导致△k_(eff)减小,从而降低最终效果。但是,对于仅在第6组(手术组)中工作的WWER-440控制组件,增加的燃耗会导致最终效果的增加。

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