氢化锆慢化熔盐堆钍铀转换性能初步分析

吴攀; 蔡翔舟; 余呈刚; 陈金根; 徐刚

doi:10.11889/j.0253-3219.2016.hjs.39.050605

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氢化锆慢化熔盐堆钍铀转换性能初步分析

更新时间：2021-05-25

- 氢化锆慢化熔盐堆钍铀转换性能初步分析
- Preliminary analysis of Th-U conversion performance in a ZrH-moderated molten salt reactor
- 核技术 2016年39卷第5期文章编号：050605
- 作者机构：
  
  1.上海大学上海 200444;
  2.中国科学院上海应用物理研究所嘉定园区上海 201800
- 作者简介：
  
  吴攀,男,1990年出生,2012年毕业于南华大学,现为硕士研究生,研究方向为反应堆中子物理计算
  陈金根,E-mail:chenjg@sinap.ac.cn
- 基金信息：
- DOI：10.11889/j.0253-3219.2016.hjs.39.050605
  中图分类号： TL329
- 收稿日期：2016-01-12，
  
  录用日期：2016-03-22，
  
  纸质出版日期：2016-01-25
- 稿件说明：
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吴攀, 蔡翔舟, 余呈刚, 等. 氢化锆慢化熔盐堆钍铀转换性能初步分析[J]. 核技术, 2016,39(5):050605

Pan WU, Xiangzhou CAI, Chenggang YU, et al. Preliminary analysis of Th-U conversion performance in a ZrH-moderated molten salt reactor[J]. Nuclear techniques, 2016, 39(5): 050605
吴攀, 蔡翔舟, 余呈刚, 等. 氢化锆慢化熔盐堆钍铀转换性能初步分析[J]. 核技术, 2016,39(5):050605 DOI： 10.11889/j.0253-3219.2016.hjs.39.050605.

Pan WU, Xiangzhou CAI, Chenggang YU, et al. Preliminary analysis of Th-U conversion performance in a ZrH-moderated molten salt reactor[J]. Nuclear techniques, 2016, 39(5): 050605 DOI： 10.11889/j.0253-3219.2016.hjs.39.050605.

摘要

中子能谱对钍基燃料在熔盐堆中的利用效率及温度反馈系数等安全问题有较大影响

所以对熔盐堆新型慢化剂的研究具有重要意义。本工作基于SCALE6计算程序

对不同几何栅元结构的氢化锆栅元组件在熔盐堆的物理性能进行了研究

分别计算了中子能谱、钍铀转换比、

233

U浓度、总温度反馈系数以及燃耗等中子物理参量。结果表明

减小六边形栅元对边距或者增加熔盐占栅元体积比可以增加钍铀转换比和改善温度反应性系数;当加入的氢化锆慢化剂体积份额为0.1时就可以将熔盐堆

233

U初始浓度降低到2.5×10

-2

以内;氢化锆慢化熔盐堆在超热谱条件下

其

233

U初装载量和超铀核素产量较小

同时堆芯较为紧凑。

Abstract

Background:

The neutron spectrum plays an important role in thorium-based fuel utilization efficiency and temperature feedback coefficient concerning reactor operation safety

so it is very important to study the new moderator material used in molten salt reactor(MSR).

Purpose:

This study aims to analyze the thorium-uranium conversion performance of a ZrH-moderated molten salt reactor and analyze the feasibility of ZrH as moderator in molten salt reactor.

Methods:

SCALE program is used to calculate neutron spectrum

thorium uranium conversion ratio

233

U concentration

total temperature feedback coefficient and burnup calculation with different lattice parameters.

Results:

The thorium uranium conversion ratio and total temperature feedback coefficient can be improved significantly by reducing lattice size or increasing salt volume ratio; the initial

233

U concentration for start reactor can be easily controlled under 2.5×10

-2

when the volume share of added ZrH is 0.1.

Conclusion:

Compared to the graphite-moderated MSR

ZrH-moderated MSR reduces initial

233

U inventory and transuraniums(TRUs) production

and makes its core more compact.

关键词

Keywords

references

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