铅冷快增殖堆物理和热工水力研究  

Physical and thermohydraulic study on lead cooled fast breeder reactor

作　　者：沈秀中[1] 杨修周[1] 于平安[1] 

机构地区：[1]上海交通大学机械与动力工程学院,上海200030

出　　处：《核技术》2003年第11期896-900,共5页Nuclear Techniques

摘　　要：对25 MW电功率铅冷快增殖堆堆芯进行了物理和热工水力概算,并将计算结果与相同功率的钠冷快增 殖堆的结果进行了分析比较。从初步概算的结果来看,铅冷快增殖堆是一种安全可行的快增殖堆堆型。A physical and thermohydraulic general estimate for the core of 25MW Lead Cooled Fast Breeder Reactor (LCFBR) has been carried out. The estimated result was compared with that of Sodium Cooled Fast Breeder Reactor (SCFBR) at the same power. The preliminary analysis showed that the LCFBR was a safe and feasible fast breeder reactor.

关 键 词：快增殖堆 铅冷却剂 初步设计 

分 类 号：TL371[核科学技术—核技术及应用]