熔盐燃料对加速器驱动的次临界堆中子学性能的影响

赵学超; 蔡翔舟; 陈金根

doi:10.11889/j.0253-3219.2018.hjs.41.080601

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熔盐燃料对加速器驱动的次临界堆中子学性能的影响

核能科学与工程 | 更新时间：2021-05-19

- 熔盐燃料对加速器驱动的次临界堆中子学性能的影响
- Study of the neutronics performance of molten salt fuel in an accelerator driven subcritical reactor
- 核技术 2018年41卷第8期文章编号：080601
- 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：
  
  [ "赵学超, 男, 1989年出生, 2011年毕业于山东大学, 现为博士研究生, 研究方向为钍铀燃料循环", "ZHAO Xuechao, male, born in 1989, graduated from Shandong University in 2011, doctoral student, focusing on Th-U fuel cycle" ]
  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)
- DOI：10.11889/j.0253-3219.2018.hjs.41.080601
  中图分类号： TL99
- 收稿日期：2018-03-16，
  
  修回日期：2018-04-12，
  
  纸质出版日期：2018-08
- 稿件说明：
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赵学超, 蔡翔舟, 陈金根. 熔盐燃料对加速器驱动的次临界堆中子学性能的影响[J]. 核技术, 2018,41(8):080601

Xuechao ZHAO, Xiangzhou CAI, Jingen CHEN. Study of the neutronics performance of molten salt fuel in an accelerator driven subcritical reactor[J]. Nuclear techniques, 2018, 41(8): 080601
赵学超, 蔡翔舟, 陈金根. 熔盐燃料对加速器驱动的次临界堆中子学性能的影响[J]. 核技术, 2018,41(8):080601 DOI： 10.11889/j.0253-3219.2018.hjs.41.080601.

Xuechao ZHAO, Xiangzhou CAI, Jingen CHEN. Study of the neutronics performance of molten salt fuel in an accelerator driven subcritical reactor[J]. Nuclear techniques, 2018, 41(8): 080601 DOI： 10.11889/j.0253-3219.2018.hjs.41.080601.

摘要

加速器驱动的次临界熔盐堆（Accelerator-Driven Subcritical Molten Salt Reactor，ADS-MSR）结合了熔盐堆与ADS的许多优点，在先进核燃料利用方面有独特的优势。为了研究熔盐燃料的使用对ADS系统堆芯的中子学性能的影响，基于MCNP（Monte Carlo N Particle Transport Code）程序，分别计算并分析了熔盐燃料对加速器驱动的次临界堆的外源质子效率、中子能谱以及钍铀转换比等参数的影响。结果表明：相较于氧化物燃料，熔盐燃料的使用将会增加对外源中子和裂变中子的慢化，并且会提高堆芯的入射质子效率。同时，由于熔盐燃料的慢化效应，FLiBe和FLi熔盐燃料燃耗初期的钍铀转换比（

）分别为1.023和1.062，略低于氧化物燃料的1.068。另一方面，熔盐燃料的在线处理会极大降低燃耗过程中的反应性损失。通过在线燃料处理和在线添料，FLi熔盐和FLiBe熔盐燃料的

分别在燃耗运行的第1年和第3年超过氧化物燃料，并且能够长期稳定在1.06和1.00左右。

Abstract

Background

Accelerator-driven subcritical molten salt reactor (ADS-MSR) has many unique advantages and features for advanced nuclear fuel utilization.

Purpose

This study aims to analyze the influence of neutronics performance of the molten salt fuel in ADS.

Methods

In this work

the Monte Carlo N particle transport code (MCNP) program was employed to calculate the proton source efficiency

the neutron spectrum and the Th-U breeding in an accelerator driven subcritical molten salt reactor.

Results

Molten salt fuels will enhance the moderation to spallation neutrons and fission neutrons while improving the proton source efficiency. The moderating effect of molten salt reduces the Th-U breeding capability at the beginning of burnup

and the

of FLi

FLiBe and oxide fuel were 1.023

1.062 and 1.068 respectively. On the other side

with on-line refueling and fuel processing

the

of FLi and FLiBe salt become higher than oxide fuel in the first year and 3rd year of the burnup

and can stabilize around 1.06 and 1.00 for a long period of time

respectively.

Conclusion

Compared to the oxide fuel

the FLi molten salt fuel has the better performance on Th-U breeding in an accelerator driven subcritical reactor.

关键词

Keywords

references

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