钍基氯盐快堆燃耗性能分析

彭一鹏; 余呈刚; 崔德阳; 夏少鹏; 朱帆; 蔡翔舟; 陈金根

doi:10.11889/j.0253-3219.2018.hjs.41.070602

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钍基氯盐快堆燃耗性能分析

核能科学与工程 | 更新时间：2021-05-19

- 钍基氯盐快堆燃耗性能分析
- Analysis of burnup performance for a molten chloride salt fast reactor based on thorium fuel
- 核技术 2018年41卷第7期文章编号：070602
- 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：
  
  [ "彭一鹏, 男, 1993年出生, 2015年毕业于哈尔滨工程大学, 现为硕士研究生, 研究方向为熔盐堆物理设计", "PENG Yipeng, male, born in 1993, graduated from Harbin Engineering University in 2015, master student, focusing on physical design on MSR" ]
  蔡翔舟, E-mail:caixz@sinap.ac.cn CAI Xiangzhou, E-mail: caixz@sinap.ac.cn
  陈金根, E-mail:chenjg@sinap.ac.cn CHEN Jingen, E-mail: chenjg@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.0253-3219.2018.hjs.41.070602
  中图分类号： TL99
- 收稿日期：2017-12-20，
  
  修回日期：2017-12-20，
  
  纸质出版日期：2018-07-10
- 稿件说明：
移动端阅览
彭一鹏, 余呈刚, 崔德阳, 等. 钍基氯盐快堆燃耗性能分析[J]. 核技术, 2018,41(7):070602

Yipeng PENG, Chenggang YU, Deyang CUI, et al. Analysis of burnup performance for a molten chloride salt fast reactor based on thorium fuel[J]. Nuclear techniques, 2018, 41(7): 070602
彭一鹏, 余呈刚, 崔德阳, 等. 钍基氯盐快堆燃耗性能分析[J]. 核技术, 2018,41(7):070602 DOI： 10.11889/j.0253-3219.2018.hjs.41.070602.

Yipeng PENG, Chenggang YU, Deyang CUI, et al. Analysis of burnup performance for a molten chloride salt fast reactor based on thorium fuel[J]. Nuclear techniques, 2018, 41(7): 070602 DOI： 10.11889/j.0253-3219.2018.hjs.41.070602.

摘要

与氟盐堆相比，氯盐快堆具有超铀核素（Transuranics，TRU）溶解度更高、中子能谱更硬、熔点更低等方面的优势。基于熔盐嬗变堆（Molten Salt Actinide Recycler and Transmuter，MOSART）的堆芯结构，采用熔盐堆在线添料和后处理程序MSR-RS（Molten Salt Reactor Reprocessing Sequence）进行分析，针对氯盐快堆的熔盐组成、后处理方式等方面进行了优化，以利于提升其增殖及嬗变性能。首先分析了不同载体盐和启动燃料对燃耗性能的影响，提出了熔盐成分优化方案；然后引入离线批处理和在线连续处理两种后方式来提升燃耗性能。结果表明：在氯盐快堆中，高重金属溶解度的NaCl更适合作为载体盐；TRU中的次锕系核素（Minor Actinides，MA）有助于提升增殖性能；采用离线批处理能够达到较好的燃耗性能，降低对后处理系统的要求。优化后的堆芯燃耗时间延长到31 a，相应的燃耗深度提高至210 GW·d·t

-1

左右，

233

U的积累量达到8300 kg，并且最终消耗了约12000 kg的TRU，嬗变率为62.1%。

Abstract

Background

Compared with the molten fluoride salt reactor

the molten chloride salt fast reactor (MCFR) has outstanding advantages in terms of transuranics (TRU) solubility

neutron spectrum and melting point

so it is very crucial to study neutron performances of the MCFR to evaluate its feasibility.

Purpose

This study aims to optimize the composition and reprocessing method of the molten salt to enhance the breeding and burnup performance of MCFR.

Methods

Based on the molten salt reactor reprocessing sequence (MSR-RS)

the effect of different carrier salt and starting fuel on burnup performance are analyzed and the composition of molten salt is optimized. Then

off-line batch reprocessing and on-line continuous reprocessing are introduced to improve burnup performance.

Results

After a series of optimization

the burnup-time is extended to 31 a

the burnup level is increased to 210GW·d·t

-1

the production of

233

U is 8300 kg

and finally 12000 kg of TRU is consumed corresponding to transmutation rate of 62.1%.

Conclusion

NaCl is a more suitable carrier salt for MCFR

and minor actinides (MA) in the TRU also helps to improve the breeding performance. Batch reprocessing can not only achieve great burnup performance but also reduces the requirement for the reprocessing system.

关键词

Keywords

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