Physical-property study on liquid fluoride-salt-cooled high temperature reactor loaded with different kinds of fuel mixtures

CHEN Liang; CHEN Jingen; LI Xiaoxiao; CAI Xiangzhou; SUN Jianyou; JIANG Dazhen; YAO Zeen

doi:10.11889/j.0253-3219.2014.hjs.37.030601

您当前的位置：

首页 >

文章列表页 >

Physical-property study on liquid fluoride-salt-cooled high temperature reactor loaded with different kinds of fuel mixtures

更新时间：2021-03-03

- Physical-property study on liquid fluoride-salt-cooled high temperature reactor loaded with different kinds of fuel mixtures
  封面论文
- NUCLEAR TECHNIQUES Vol. 37, Issue 3, Article number: 030601(2014)
- 作者机构：
  
  1. 兰州大学核科学与技术学院,兰州,730000
  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：
- 基金信息：
- DOI：10.11889/j.0253-3219.2014.hjs.37.030601
  CLC：
- Published：14 March 2014
- 稿件说明：
移动端阅览
CHEN Liang, CHEN Jingen, LI Xiaoxiao, et al. Physical-property study on liquid fluoride-salt-cooled high temperature reactor loaded with different kinds of fuel mixtures[J]. Nuclear techniques, 2014, 37(3): 030601
DOI：

CHEN Liang, CHEN Jingen, LI Xiaoxiao, et al. Physical-property study on liquid fluoride-salt-cooled high temperature reactor loaded with different kinds of fuel mixtures[J]. Nuclear techniques, 2014, 37(3): 030601 DOI： 10.11889/j.0253-3219.2014.hjs.37.030601.

摘要

液态氟盐冷却高温堆是第四代反应堆中的一种具有极大优势的堆型，对其燃料的研究工作具有重要的意义。本工作采用SCALE5.1程序包，对六种不同燃料组合在高温球床堆中的物理性能进行了研究，分别比较了剩余反应性、等效满功率运行天数、燃耗和中子能谱等重要参数。结果显示，采用233U或235U启堆时，使用232Th的实际转换成裂变材料的量不如使用238U转换的多，并会消耗更多的核燃料；采用239Pu启堆时，使用232Th可使反应堆维持较长的时间，而使用238U却导致反应堆很快不能自持。研究表明，从节约核燃料和延长堆芯寿期的角度看，在不进行在线换料后处理的情况下，232Th在热堆中的表现不如238U，但在超热堆中238U的表现不如232Th。

Abstract

Background: Liquid fluoride-salt-cooled high temperature reactor

one of the GEN-IV reactors

has great advantages comparatively

and the research on its fuel is of great significance. Purpose: The aim is to study the physical properties of high-temperature pebble-bed reactors loaded with six different fuel mixtures. Methods: We used SCALE5.1 package to compute some important parameters like excess reactivity

full power operation days

burnup and neutron spectrum. Results: The results show that the true conversions of 232Th are much less than those of 238U when mixed with 233U or 235U. With 239Pu for starting

232Th contributes to making the reactor running longer than that with 238U. Conclusion: With respect to saving fuel and extending the life of the core

without online refueling and reprocessing

232Th is underperformed in thermal reactor compared with 238U

however

it is the opposite in epithermal neutron reactor.Cited

关键词

Keywords

references

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

No data

Related Author

No data

Related Institution

No data

AI问答

Address：2019 Jialuo Road, Jiading, Shanghai, China Postal code：201800
Tel：021-39194977 Email：LHB@sinap.ac.cn
Technical support is provided by Beijing Founder electronics co., LTD 沪ICP备05005479号-1 京公网安备11010802024621
It is recommended to read the content of this site in Chrome&IE9+. Please switch to extreme mode in browser 360.
Cookies We use cookies to help provide and enhance our service and tailor content. By continuing, you agree to the use of cookies.
Total Visits：881246 Visits Today：773

⁰