首页> 外文会议>International Topical Meeting on Nuclear Reactor Thermal Hydraulics >3-D MODELLING OF A SUPERPHéNIX BENCHMARK WITH SERPENT AND PARCS FOR COUPLED SIMULATION WITH PARCS/ATHLET
【24h】

3-D MODELLING OF A SUPERPHéNIX BENCHMARK WITH SERPENT AND PARCS FOR COUPLED SIMULATION WITH PARCS/ATHLET

机译:3-D使用Parcs / Athlet耦合模拟的Superphénix基准测试与PARCS / Athlet的模拟

获取原文

摘要

Most of the safety criteria for Sodium cooled Fast Reactors (SFR) are local core parameters.Thus, application of 3-D neutron kinetic and thermal-hydraulic coupled codes includingdetailed modelling of core expansion effects is mandatory for best estimate evaluations ofsafety margins. A recently published benchmark related to Superphénix offers the opportunityto validate codes and methods for SFR safety assessment. This requires the generation of fewgroupcross-sections. Since whole core Serpent Monte Carlo models for production of suchcross-section libraries would be computationally costly (and the standard 2-D approach mayintroduce unnecessary large approximations), 3-D models of each sub-assembly type ininfinite radial lattice configurations have been created with Serpent. To simplify the handlingof temperature dependent geometric changes, a pre-processor for generation of temperaturedriven expansion of geometry and material densities has been developed and implemented inthe GRS core simulator KMACS. These cross-sections are then used to evaluate effectivemultiplication factors and 3-D distributions of power density using PARCS for different coreconfigurations. The results are compared with the reference calculation and with experimentaldata provided with the benchmark. In the next step, a simple ATHLET parallel channel opencore model has been developed for coupled PARCS/ATHLET first transient test calculations.This paper describes in detail the models and techniques used for the generation of the fewgroupparameterized cross section libraries, the PARCS model and the ATHLET open coremodel and first transient test calculations.
机译:大多数的中钠的安全标准冷快堆(SFR)是当地的核心参数。因此,3-d中子动能和热工水力耦合码的应用,包括核心膨胀效应详细的模型是强制性的最佳估计评估安全边际。有关Superphénix最近公布的基准测试提供了机会以验证SFR安全评价规范和方法。这需要fewgroup的一代交叉区域。由于整芯蛇蒙特卡罗模型制作等横截面库将是计算成本高(和标准2-d的方法可以引入不必要的大的近似值),每个的3-d模型子组件键入无限的径向晶格结构已与蛇创建。为了简化处理的依赖于温度的几何变化,预处理器,用于生成温度的几何形状和材料密度的动膨胀已经制定并实施中所述GRS芯模拟器KMACS。这些横截面然后被用来评估有效乘法因数和功率密度的3-d分布使用PARCS对于不同的核心配置。将其结果与所述基准计算,并与实验相比数据设置有基准。在下一步骤中,一个简单的ATHLET平行通道开放核心模式已被开发用于耦合PARCS / ATHLET第一瞬态测试计算。本文详细介绍了用于fewgroup的生成模式和技术参数截面图书馆,PARCS模型和ATHLET开核模型和第一瞬态测试计算。

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