超临界水冷堆压力容器设计  

Design of Supercritical Water-cooled Reactor Pressure Vessel

作　　者：王小彬[1] 李玉光[1] 罗英[1] 方才顺[1] 

机构地区：[1]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,工程师成都610041

出　　处：《一重技术》2015年第3期18-21,共4页CFHI Technology

摘　　要：基于中国百万千瓦级超临界水冷堆(CSR1000)总体性能参数,对超临界水冷堆(SCWR)反应堆压力容器进行研究,提出SCWR反应堆压力容器总体设计思路,从主腔室和出口腔室材料选择上提出多种具有应用前景的压力容器设计方案:如采用SA 508 3级Ⅰ类、SA 508 3级Ⅱ类钢或SA 508 4N级Ⅰ类钢的主腔室和采用Inconel690合金或9Cr-1Mo-V钢的出口腔室。Based on Main General Design Parameters of CSR1000 （the 1000 MW Super-critical Water Reactor in China） , the paper focuses on the research of design project for SCWR （Super-critical Water Reactor） RPV （Reactor Pressure Vessel） . The general design theory of SCWR RPV has been forwarded and the plentiful design proposal with nice foreground of RPV has been obtained in lhis study, for example,/he nmin cavity adopting SA 508 grade 3 class 1 steel or SA508 grade 3 class 2 steel or SA 508 grade 4N class I steel and the exit cavity adopting Ineonel 690 alloy or 9Cr-IMo-V steel, thereby to establish a favorable teehnology foundation for the later engineering prugress and overall technology research.

关 键 词：超临界水冷堆 反应堆压力容器 设计思路 设计方案 

分 类 号：TL351.6[核科学技术—核技术及应用]