Physical and thermohydraulic study on lead cooled fast breeder reactor

SHEN Xiuzhong YANG Xiuzhou YU Ping’an

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Physical and thermohydraulic study on lead cooled fast breeder reactor

更新时间：2021-03-12

- Physical and thermohydraulic study on lead cooled fast breeder reactor
- NUCLEAR TECHNIQUES Issue 11, (2003)
- 作者机构：
  
  1. 上海交通大学机械与动力工程学院
  2. 上海交通大学机械与动力工程学院,上海,200030
- 作者简介：
- 基金信息：
- DOI：
  CLC： TL433
- Published：01 November 2003
- 稿件说明：
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[1]沈秀中,杨修周,于平安.铅冷快增殖堆物理和热工水力研究[J].核技术,2003(11):896-900.

SHEN Xiuzhong YANG Xiuzhou YU Ping’an. Physical and thermohydraulic study on lead cooled fast breeder reactor[J]. Nuclear techniques, 2003, (11): 896-900.
[1]沈秀中,杨修周,于平安.铅冷快增殖堆物理和热工水力研究[J].核技术,2003(11):896-900. DOI：

SHEN Xiuzhong YANG Xiuzhou YU Ping’an. Physical and thermohydraulic study on lead cooled fast breeder reactor[J]. Nuclear techniques, 2003, (11): 896-900. DOI：

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。

Abstract

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.

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