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首页> 外文会议>14th International Conference on Nuclear Engineering(ICONE14) vol.5 >Safety Criticality Standards using the French CRISTAL Code Package Application to the AREVA NP UO_2 Fuel Fabrication Plant
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Safety Criticality Standards using the French CRISTAL Code Package Application to the AREVA NP UO_2 Fuel Fabrication Plant

机译：在法国AREVA NP UO_2燃料加工厂使用法国CRISTAL程序包应用程序的安全关键标准

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Criticality safety evaluations implement requirements to proof of sufficient sub critical margins outside of the reactor environment for example in fuel fabrication plants. Basic criticality data (i.e., criticality standards) are used in the determination of sub critical margins for all processes involving plutonium or enriched uranium. There are several criticality international standards, e.g., ARH-600, which is one the US nuclear industry relies on.rnThe French Nuclear Safety Authority (DGSNR and its advising body IRSN) has requested AREVA NP to review the criticality standards used for the evaluation of its Low Enriched Uranium fuel fabrication plants with CRISTAL VO, the recently updated French criticality evaluation package. Criticality safety is a concern for every phase of the fabrication process including UF_6 cylinder storage, UF_6-UO_2 conversion, powder storage, pelletizing, rod loading, assembly fabrication, and assembly transportation.rnUntil 2003, the accepted criticality standards were based on the French CEA work performed in the late seventies with the APOLLO1 cell/assembly computer code. APOLLO1 is a spectral code, used for evaluating the basic characteristics of fuel assemblies for reactor physics applications, which has been enhanced to perform criticality safety calculations.rnThroughout the years, CRISTAL, starting with APOLLO1 and MORET 3 (a 3D Monte Carlo code), has been improved to account for the growth of its qualification database and for increasing user requirements. Today, CRISTAL V0 is an up-to-date computational tool incorporating a modern basic microscopic cross section set based on JEF2.2 and the comprehensive APOLLO2 and MORET 4 codes.rnAPOLLO2 is well suited for criticality standards calculations as it includes a sophisticated self shielding approach, a Pij flux determination, and a 1D transport (S_n) process. CRISTAL VO is the result of more than five years of development work focusing on theoretical approaches and the implementation of user-friendly graphical interfaces.rnDue to its comprehensive physical simulation and thanks to its broad qualification database with more than a thousand benchmark/calculation comparisons, CRISTAL VO provides outstanding and reliable accuracy for criticality evaluations for configurations covering the entire fuel cycle (i.e. from enrichment, pellet/assembly fabrication, transportation, to fuel reprocessing).rnAfter a brief description of the calculation scheme and the physics algorithms used in this code package, results for the various fissile media encountered in a UO_2 fuel fabrication plant will be detailed and discussed.
机译：临界安全性评估实施要求，以证明在反应堆环境之外（例如在燃料制造厂中）有足够的次临界裕度。基本临界数据（即临界标准）用于确定涉及involving或富铀的所有过程的亚临界裕度。有几种关键性国际标准，例如ARH-600，这是美国核工业所依赖的一种。rn法国核安全局（DGSNR及其建议机构IRSN）已要求AREVA NP审查用于评估核电的关键性标准。其具有最近更新的法国关键性评估包CRISTAL VO的低浓铀燃料制造厂。关键安全性是制造过程的每个阶段都需要考虑的问题，包括UF_6气瓶存储，UF_6-UO_2转换，粉末存储，造粒，棒料装载，装配制造和装配运输。七十年代末使用APOLLO1单元/装配体计算机代码执行的工作。 APOLLO1是一种光谱代码，用于评估反应堆物理应用的燃料组件的基本特性，并已进行增强以执行临界安全性计算.rn多年来，CRISTAL以APOLLO1和MORET 3（3D蒙特卡洛代码）开头，已进行了改进，以适应其资格数据库的增长和用户需求的增长。如今，CRISTAL V0是最新的计算工具，结合了基于JEF2.2和全面的APOLLO2和MORET 4代码的现代基本微观横截面集.rnAPOLLO2包括复杂的自屏蔽功能，非常适合于临界标准计算。方法，Pij通量确定和一维输运（S_n）过程。 CRISTAL VO是五年多的开发工作的结果，该开发工作专注于理论方法和用户友好的图形界面的实现。由于其全面的物理模拟，并且由于其广泛的认证数据库以及超过一千个基准/计算比较， CRISTAL VO为涵盖整个燃料循环（即从浓缩，丸粒/组件制造，运输到燃料再处理）的配置的关键性评估提供了出色而可靠的准确性。rn在简要说明了此代码中使用的计算方案和物理算法之后软件包中，将详细讨论UO_2燃料制造工厂遇到的各种裂变介质的结果。

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