基于熔盐快堆的模型优化与Th-U增殖性能研究

李光超; 邹杨; 余呈刚; 孙建友; 陈金根; 徐洪杰

doi:10.11889/j.0253-3219.2017.hjs.40.020603

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基于熔盐快堆的模型优化与Th-U增殖性能研究

核能科学与工程 | 更新时间：2021-05-19

- 基于熔盐快堆的模型优化与Th-U增殖性能研究
- Model optimization and analysis of Th-U breeding based on MSFR
- 核技术 2017年40卷第2期文章编号：020603
- 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.中国科学院先进核能创新研究院上海 201800
  3.中国科学院大学北京 100049
- 作者简介：
  
  [ "李光超, 男, 1987年出生, 2011年毕业于南京航空航天大学, 现为博士研究生, 研究方向为熔盐堆物理设计及Th-U燃料循环", "LI Guangchao, male, born in 1987, graduated from Nanjing University of Aeronautics and Astronautics in 2011, doctoral student, focusing on physical design and Th-U cycle on MSR" ]
  陈金根, E-mail:chenjg@sinap.ac.cn CHEN Jingen, ,E-mail:chenjg@sinap.ac.cn
  徐洪杰, E-mail:xuhongjie@sinap.ac.cn XU Hongjie, E-mail:xuhongjie@sinap.ac.cn
- 基金信息：
  
  中国科学院战略性先导科技专项(XDA02010000);若干关键问题研究项目(QYZDY-SSW-JSC016);国家自然科学基金(91326201)
- DOI：10.11889/j.0253-3219.2017.hjs.40.020603
  中图分类号： TL426
- 收稿日期：2016-09-28，
  
  修回日期：2016-12-19，
  
  纸质出版日期：2017-02-10
- 稿件说明：
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李光超, 邹杨, 余呈刚, 等. 基于熔盐快堆的模型优化与Th-U增殖性能研究[J]. 核技术, 2017,40(2):020603

Guangchao LI, Yang ZOU, Chenggang YU, et al. Model optimization and analysis of Th-U breeding based on MSFR[J]. Nuclear techniques, 2017, 40(2): 020603
李光超, 邹杨, 余呈刚, 等. 基于熔盐快堆的模型优化与Th-U增殖性能研究[J]. 核技术, 2017,40(2):020603 DOI： 10.11889/j.0253-3219.2017.hjs.40.020603.

Guangchao LI, Yang ZOU, Chenggang YU, et al. Model optimization and analysis of Th-U breeding based on MSFR[J]. Nuclear techniques, 2017, 40(2): 020603 DOI： 10.11889/j.0253-3219.2017.hjs.40.020603.

摘要

作为四代堆6种候选堆型中唯一的液态燃料反应堆，熔盐堆对未来核能和钍资源利用具有重要意义，特别是熔盐快堆（Molten Salt Fast Reactor，MSFR）还具有较大的增殖比和较好的温度负反馈。由于启动新的熔盐快堆需要较高的燃料装载量，若能改善MSFR的增殖性能，则有利于提高

233

U产量并缩短燃料倍增时间。首先应用SCALE6.1针对MSFR的径向增殖盐、新增轴向增殖盐和新增石墨反射层这三方面分析了初始增殖比，同时从核素吸收率角度说明增殖比变化的原因和MSFR的设计不足并对其进行了优化；然后应用基于SCALE6.1开发的熔盐堆在线处理模块（Molten Salt Reactor Reprocessing Sequence，MSR-RS）进行燃耗分析。结果表明，新增轴向增殖盐可以进一步提高增殖性能；新增石墨反射层可以节省增殖盐装载量。改进后的堆型运行时增殖比可以维持在1.1以上，

233

U年产量提高至133 kg，倍增时间缩短至36 a，并且堆芯在整个运行寿期都能保持足够的温度负反馈。

Abstract

Background

As the only one of liquid fuel reactor among the six candidate reactors chosen by the Generation IV International Forum (GIF)

Molten Salt Reactor (MSR) shows great potential for future nuclear energy and thorium usage

especially for Molten Salt Fast Reactor (MSFR) with characters of high Th-U Breeding Ratio (BR) and large negative Temperature Coefficient of Reactivity (TCR).

Purpose

Th-U breeding capacity of MSFR is expected to be further improved for more

233

U production and shorter Double Time (DT)

and burn-up analysis is necessary to demonstrate the breeding characters with time

as well as TCR for safety.

Methods

Based on SCALE6.1

three aspects are explored including fertile in radial direction

newly added fertile in axial direction and appended graphite reflector

followed with explanations from the point of nuclide reaction rate. Furthermore

burn-up analysis is carried out with time by using the self-developed code Molten Salt Reactor Reprocessing Sequence (MSR-RS) specifically for on-line reprocessing of MSR.

Results

Initial BR of 1.17 is obtained when axial fertile is included

and about 50% of fertile salt is saved with graphite reflector. BR above 1.1 in equilibrium and DT of 36 a are achieved

and the production of

233

U is about 133 kg·a

-1

while TCR can be kept at about -6×10

-5

-1

Conclusion

Newly added axial fertile improves the BR obviously

while about half inventory of thorium can be saved with graphite reflector. The self-developed module MSR-RS is suitable for simulating the reprocessing of MSR

and

233

U production for the optimized geometry increases markedly while TCR is kept negative enough at all the running time for safety.

关键词

Keywords

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