正常运行工况熔盐堆主回路衰变热特性研究

周波; 严睿; 邹杨; 杨璞; 于世和; 刘亚芬

doi:10.11889/j.0253-3219.2018.hjs.41.040602

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正常运行工况熔盐堆主回路衰变热特性研究

核能科学与工程 | 更新时间：2021-05-19

- 正常运行工况熔盐堆主回路衰变热特性研究
- Analysis of decay heat in primary loop of molten salt reactor under normal conditions
- 核技术 2018年41卷第4期文章编号：040602
- 作者机构：
  
  1.中国科学院上海应用物理研究所嘉定园区上海 201800
  2.中国科学院大学北京 100049
- 作者简介：
  
  [ "周波, 男, 1985年出生, 2012年毕业于哈尔滨工程大学, 现为博士研究生, 研究方向为反应堆物理设计与源项分析", "ZHOU Bo, male, born in 1985, graduated from Harbin Engineering University in 2012, doctoral student, focusing on reactor physics design and source term analysis" ]
  邹杨, E-mail:zouyang@sinap.ac.cn ZOU Yang, E-mail: zouyang@sinap.ac.cn
- 基金信息：
  
  中国科学院战略性先导科技专项(XDA02010000);Thorium Uranium Fuel Cycle Characteristics and Key Problem Research Project(QYZDY-SSW-JSC016)
- DOI：10.11889/j.0253-3219.2018.hjs.41.040602
  中图分类号： TL329
- 收稿日期：2017-11-24，
  
  修回日期：2018-01-05，
  
  纸质出版日期：2018-04-10
- 稿件说明：
移动端阅览
周波, 严睿, 邹杨, 等. 正常运行工况熔盐堆主回路衰变热特性研究[J]. 核技术, 2018,41(4):040602

Bo ZHOU, Rui YAN, Yang ZOU, et al. Analysis of decay heat in primary loop of molten salt reactor under normal conditions[J]. Nuclear techniques, 2018, 41(4): 040602
周波, 严睿, 邹杨, 等. 正常运行工况熔盐堆主回路衰变热特性研究[J]. 核技术, 2018,41(4):040602 DOI： 10.11889/j.0253-3219.2018.hjs.41.040602.

Bo ZHOU, Rui YAN, Yang ZOU, et al. Analysis of decay heat in primary loop of molten salt reactor under normal conditions[J]. Nuclear techniques, 2018, 41(4): 040602 DOI： 10.11889/j.0253-3219.2018.hjs.41.040602.

摘要

基于Mathematica 7.0建立了熔盐堆（Molten Salt Reactor，MSR）主回路系统衰变热流动模型，并与参考程序ORIGENS在静态燃耗下的计算结果以及熔盐实验堆（Molten Salt Reactor Experiment，MSRE）衰变热结果进行了初步验证，相对偏差分别在±4%和±2.76%的范围内符合较好。对2 MW液态燃料钍基熔盐实验堆（Thorium Molten Salt Reactor-Liquid Fuel 1，TMSR-LF1）正常运行工况下主回路系统管道及设备内的衰变热分布进行了定量分析。结果表明：启堆达到满功率和设定流量后约20 s各区域衰变热快速积累，随后便开始平缓上升并趋平衡。平衡时堆芯活性区衰变热占总衰变热的46.7%，上腔室、热管段#1、主泵、热管段#2、换热器、冷管段及下腔室区域分别占比31.8%、1.21%、14.6%、0.89%、2.21%、1.67%和0.94%。所建立的分析方法及结论可为熔盐堆主回路系统的热工水力安全分析、余热排出系统设计、反应堆功率调节与安全控制提供重要参考。

Abstract

Background

The fissile nuclides in the molten salt reactor (MSR) will produce a large number of fission products under normal operation conditions

which would fill the entire primary loop system. The decay of the fission products would generate heat all the time

even though the fission power stopped. The accurate analysis of the decay heat has great significance on the safety analysis of the primary loop pipe and equipment.

Purpose

This study aims to establish a numerical model for analyzing the decay heat of the primary loop.

Methods

The numerical flow model of the decay heat was established for 2 MW MSR (Thorium Molten Salt Reactor-Liquid Fuel 1

TMSR-LF1) designed by Shanghai Institute of Applied Physics (SINAP)

Chinese Academy of Sciences

and then solved by using Mathematica 7.0. The simulation results of the static burning of TMSR-LF1 of SINAP and molten salt reactor experiment (MSRE) of Oak Ridge National Laboratory

were compared with that of ORIGENS program

the deviations are within the range of ±4% and ±2.76% respectively. The decay heat distribution in primary pipe and equipments of the primary loop system under normal operating conditions of TMSR-LF1 was quantitatively analyzed to find the distribution rule of decay heat under different flow rates.

Results

The deviations of decay heat for TMSR-LF1 and MSRE

calculated by Mathematica and ORIGENS

are within the range of ±4% and ±2.76% respectively

under normal operating conditions. The decay heat accumulated rapidly in each region about 20 s after start-up of the reactor in full power and flow rate

and then began to rise slowly and tend to be an equilibrium value. After equilibrium

decay heat of core active area account for 46.7% of the total decay heat

and the upper plenum

the hot leg#1

the main pump

the hot leg#2

the heat exchanger

the cold leg and the lower plenum area accounted for 31.8%

1.21%

14.6%

0.89%

2.21%

1.67% and 0.94% respectively.

Conclusion

The established analytical method and conclusions can provide important reference for thermal hydraulic safety analysis

residual removal system design

reactor power regulation and safety control.

关键词

Keywords

references

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