SCWR堆芯和主要系统方案研究及初步分析  

Study and Preliminary Analysis of Core and Main System Design of SCWR

作　　者：李虹波 杨珏 程旭[1,2] 单建强[3] 曹良志[3] 刘晓晶[2] 

机构地区：[1]中科华核电技术研究院,广东深圳518026 [2]上海交通大学,上海200240 [3]西安交通大学,陕西西安710049

出　　处：《原子能科学技术》2013年第11期2085-2091,共7页Atomic Energy Science and Technology

摘　　要：本文提出一种新的超临界水堆(SCWR)技术方案,包括双排棒正方形闭式燃料组件、压力容器式低泄漏堆芯、非能动安全系统、反应堆控制系统、滑压启动方案和蒸汽循环系统等。开展了堆芯物理热工耦合计算分析、子通道热工水力分析、典型事故分析、控制系统分析、系统稳定性分析、启动过程分析。计算结果表明,提出的SCWR方案满足设计准则要求,是一种合理可行的SCWR技术方案。A new concept of SCWR was studied, including closed square fuel assembly with double-row rods, low-leakage core of pressure vessel type reactor, passive safety system, reactor control system, sliding-pressure start-up scheme, steam circulation system, etc. The analyses of coupled neutronics and thermal-hydraulics, sub-channel, typical accidents, control system, system stability and start-up process were carried out. The calculating results show that the major design of the core and system fulfils the design criteria, and the SCWR design concept is balanced and feasible.

关 键 词：超临界水堆 堆芯 非能动安全系统 反应堆控制系统 滑压启动 

分 类 号：TK124[动力工程及工程热物理—工程热物理]