超临界水反应堆传热分析  

Supercritical Water Reactor Heat Transfer Analysis

作　　者：舒曦 SHU Xi(China Nuclear Power Operation Management Co.,Ltd.,Run 2,Zhejiang Haiyan 314300)

机构地区：[1]中核核电运行管理有限公司运行二处,浙江海盐314300

出　　处：《科技视界》2018年第5期51-52,共2页Science & Technology Vision

摘　　要：超临界水堆(SCWR)是是被国际上选定为第四代核电系统长远开发的六种堆型之一,是在现有的轻水堆和超临界火电基础上开发出革新型设计。在超临界水堆的堆芯设计过程中,棒束间子通道内冷却剂流动的换热情况和子通道间的湍流交混系数的关系式是重要的参考数据。本文采用最目前世界上流行模拟软件fluent,利用gambit对子通道进行几何建模,主要分析目标为子通道间湍流交混系数β和对流换热系数h,得到换热系数在子通道中沿轴向的变化情况和子通道间湍流交混系数β在不同入口工况下的变化情况,最后拟出湍流交混系数通用经验关系式。Supercritical water reactor(SCWR)is one of the six reactor types selected by the international community for long-term development of the fourth-generation nuclear power system.It is based on existing light water reactors and supercritical thermal power.Design.In the core design process of the supercritical water reactor,the relationship between the heat transfer conditions of the coolant flow in the sub-channels and the turbulent cross-mixing coefficient between the sub-channels is an important reference data.This paper adopts fluent,the most popular simulation software in the world,and uses gambit to geometrically model the subchannels.The main target is to analyze the turbulent cross-mixing coefficientβand convection heat transfer coefficient h between the subchannels,and obtain the heat transfer coefficient along the axis in the subchannel.The variation of turbulence and the variation of the turbulent cross-mixing coefficientβbetween the subchannels under different inlet conditions,and finally the general empirical relationship of the turbulent blending coefficient.

关 键 词：超临界水堆(SCWR) 模拟软件fluent 湍流交混系数通用经验关系式 

分 类 号：TK124[动力工程及工程热物理—工程热物理]