首页> 外文会议>International topical meeting on nuclear reactor thermal hydraulics >DEVELOPMENT OF THE FHR ADVANCED NATURAL CIRCULATION ANALYSIS (FANCY) CODE
【24h】

DEVELOPMENT OF THE FHR ADVANCED NATURAL CIRCULATION ANALYSIS (FANCY) CODE

机译:FHR高级自然循环分析(FANCY)代码的开发

获取原文

摘要

The University of California, Berkeley (UCB) is performing thermal hydraulics safety analysis to develop the technical basis for design and licensing of fluoride-salt-cooled, high-temperature reactors (FHRs). FHR designs investigated by UCB use natural circulation for emergency, passive decay heat removal when normal decay heat removal systems fail. The FHR advanced natural circulation analysis (FANCY) code has been developed for assessment of passive decay heat removal capability and safety analysis of these innovative system designs. The FANCY code uses a one-dimensional, semi-implicit scheme to solve for pressure-linked mass, momentum and energy conservation equations. Graph theory is used to automatically generate a staggered mesh for complicated pipe network systems. Heat structure models have been implemented for three types of boundary conditions (Dirichlet, Neumann and Robin boundary conditions). Heat structures can be composed of several layers of different materials, and are used for simulation of heat structure temperature distribution and heat transfer rate. Control models are used to simulate sequences of events or trips of safety systems. A proportional-integral controller is also used to automatically make thermal hydraulic systems reach desired steady state conditions. A point kinetics model is used to model reactor kinetics behavior with temperature reactivity feedback. The underlying large sparse linear systems in these models are efficiently solved by using direct and iterative solvers provided by the SuperLU code on high performance machines. Input interfaces are designed to increase the flexibility of simulation for complicated thermal hydraulic systems. Detailed code-to-code comparison with established thermal hydraulic system codes such as RELAP5, and validation against experimental data from UCB's Compact Integral Effects Test facility, are performed in a companion paper. This paper mainly focuses on the methodology used to develop the FANCY code, and safety analysis of the Mark 1 pebble-bed FHR under development at UCB is performed.
机译:加利福尼亚大学伯克利分校(UCB)正在进行热力学安全性分析,以开发氟化物盐冷却的高温反应堆(FHR)的设计和许可技术基础。 UCB研究的FHR设计将自然循环用于正常衰减排热系统出现故障时的紧急,被动衰减排热。已开发了FHR高级自然循环分析(FANCY)代码,用于评估这些创新系统设计的被动衰减排热能力和安全性分析。 FANCY代码使用一维半隐式方案来求解与压力相关的质量,动量和能量守恒方程。图论用于为复杂的管网系统自动生成交错网格。已经针对三种类型的边界条件(Dirichlet,Neumann和Robin边界条件)实施了热结构模型。热结构可以由几层不同的材料组成,并用于模拟热结构的温度分布和传热速率。控制模型用于模拟安全系统事件或跳闸的顺序。比例积分控制器还用于自动使热力液压系统达到所需的稳态条件。点动力学模型用于对具有温度反应性反馈的反应器动力学行为进行建模。通过在高性能计算机上使用SuperLU代码提供的直接和迭代求解器,可以有效地解决这些模型中底层的大型稀疏线性系统。输入接口旨在提高复杂热力液压系统仿真的灵活性。与已建立的热力液压系统代码(例如RELAP5)进行详细的代码对代码比较,并根据UCB的紧凑型整体效果测试工具对实验数据进行验证,该过程在随附的论文中进行。本文主要关注于开发FANCY代码的方法,并对UCB正在开发的Mark 1卵石床FHR进行了安全性分析。

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