超临界水冷堆耦合条件下水棒热工特性分析  

Thermal Characteristics Analysis of Water-rod in SCWR at Coupling Condition

作　　者：周涛[1] 程万旭[1] 刘亮[1] 孙灿辉[1] 陈娟[1] 

机构地区：[1]华北电力大学核热工安全与标准化研究所,北京102206

出　　处：《原子能科学技术》2013年第11期2014-2019,共6页Atomic Energy Science and Technology

基　　金：国家重点基础研究发展计划资助项目(2007CB209800);中国核动力研究设计院核反应堆系统设计技术重点实验室资助项目(2011-153)

摘　　要：超临界水冷堆中需要单独设计水棒结构,水棒中流过慢化剂水使得堆芯得到充分慢化。本文采用日本设计堆型作为研究对象,自主设计S型、D1型、D2型3种不同水棒结构,并编制物理热工耦合程序,得到不同水棒结构及D2型水棒结构不同内层水棒外边长条件下慢化剂密度、冷却剂和慢化剂的平均密度及功率的轴向分布。结果表明:D2型双层水棒具有更均匀的慢化剂温度分布和轴向功率分布,随着内层水棒外边长的增大,轴向慢化剂密度均值有所提高。The structure of water-rod is designed separately in supercritical water-cooled reactor. The water in water-rod makes the core well moderated. Based on the SCWR neutronic/thermal-hydraulic coupling code programmed by authors, the core design of Japan was studied. Considering three types of water-rods designed by ourselves, which named S type, D1 type and D2 type, and different side lengths of inner water-rod, the distributions of moderator density, average density and axial power under each condition were obtained. The results show that the D2 type has more uniform distributions of moderator density, average density and axial power. Axial average moderator density increases with the length of outer side of inner water-rod.

关 键 词：超临界水冷堆 耦合 水棒 传热 

分 类 号：TL371[核科学技术—核技术及应用]