首页> 外文会议>International Conference on Nuclear Criticality Safety >Implementation and Validation of Reference Sensitivity Profile Calculations in TRIPOLI4
【24h】

Implementation and Validation of Reference Sensitivity Profile Calculations in TRIPOLI4

机译:Tripoli4参考敏感性配置文件计算的实现与验证

获取原文

摘要

In current neutron transport calculations, particularly on continuous-energy Monte-Carlo codes, the major source of uncertainty is coming from nuclear data. In order to improve nuclear data evaluations, integral experiments are used. Feedback is then precisely obtained by re-estimating cross-section levels and correlations according to their sensitivity. K_(eff)-sensitivity coefficients are traditionally obtained using deterministic codes since hands-on methods were not yet implemented in continuous energy Monte Carlo codes. In this paper, an Iterated-Fission-Probability-based method newly developed in the continuous energy Monte Carlo code TRIPOLI-4 will be used to calculate sensitivity coefficient breakdown on isotopes and reactions and results will be compared to those of ERANOS deterministic code. Objective is twofold: to show the reliability of the new TRIPOLI-4 method and to identify where and why profiles are slightly different. Sensitivity profiles, forward and adjoint fluxes are thus meticulously compared using a fine 1968-group energy structure. An OECD international benchmark (Uncertainty Analysis for Criticality Safety Assessment - UACSA - Phase III) is taken as working example to enforce validation and to compare to independent results (e.g. MCNP-6). This benchmark is constituted of two bare spheres filled with homogeneous mixture of uranium and polyethylene (respectively 2% and 50% U-235 enrichments) and gives an overview of issues encountered in thermal reactor cores. Several energy-group structures (1968G, 172G, 33G) are also tested in ERANOS to identify multi-group and implicit effects. Lessons learnt are that continuous Monte Carlo methods seem to be mature and compare well with deterministic codes. Only damper the U-238 elastic - and on certain conditions the U-238 capture - sensitivity coefficient for which difference can reach 30% between TRIPOLI-4 and ERANOS. Indeed concerning U-238, implicit effects are emphasized and multi-group theory remains limited by hypothesis; even a 1968-group structure is not refined enough to properly calculate U-238 elastic scattering k_efrsensitivity. This reference 3D continuous-energy sensitivity capability in TRIPOLI4-IFP will be extensively used in the uncertainty automated tool RIB of the French Criticality-Safety package CRISTAL.
机译:在目前的中子运输计算中,特别是在连续能量蒙特卡罗代码上,主要不确定性的主要来源来自核数据。为了改善核数据评估,使用整体实验。然后通过重新估计根据它们的灵敏度来精确地获得反馈。使用确定性码来获得k_(eff) - 敏感系数,因为尚未在连续能量蒙特卡罗代码中实现动手方法。在本文中,在连续能量蒙特卡罗代码Tripoli-4中新开发的基于迭代裂变的方法将用于计算同位素的灵敏度系数和反应,结果将与伊朗多斯确定性代码的结果进行比较。目标是双重的:以展示新的黎波里-4方法的可靠性,并识别概况略有不同的位置和为什么为什么。因此,使用精细的1968个组能量结构,因此精细地比较了灵敏度简档,正向和伴随通量。经合组织国际基准(关键安全评估的不确定性分析 - UACSA - 阶段III)作为执行验证的工作示例,并与独立结果进行比较(例如MCNP-6)。该基准测试由填充铀和聚乙烯的均匀混合物的两个裸球(分别为2%和50%U-235富集),并概述了热反应器核心中遇到的问题。在厄尔诺斯也测试了几种能量组结构(1968g,172g,33g),以识别多组和隐性效果。经验教训是,连续的蒙特卡罗方法似乎是成熟的,与确定性码相比很好。只有阻尼器U-238弹性 - 以及某些条件,U-238捕获 - 灵敏度系数可以在Trigoli-4和狼人之间达到30%。实际上有关U-238,强调隐含的影响,多组理论仍然受到假设的限制;即使是1968个组结构也没有足够精制,以适当地计算U-238弹性散射K_EFRSensity。 Tripoli4-IFP中的该参考3D连续能量灵敏度能力将广泛用于法式临界安全包压缩的不确定自动化工具肋。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号