一种液态燃料熔盐堆堆芯流量分配设计

周振华; 潘登; 陈玉爽; 黄建平; 余笑寒; 王纳秀

doi:10.11889/j.0253-3219.2016.hjs.39.050601

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一种液态燃料熔盐堆堆芯流量分配设计

更新时间：2021-05-25

- 一种液态燃料熔盐堆堆芯流量分配设计
  封面论文
- Core flow distribution design of molten salt reactor with liquid fuel
- 核技术 2016年39卷第5期文章编号：050601
- 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.中国科学院大学北京 100049
- 作者简介：
  
  周振华,男,1988年出生,2013年毕业于华东理工大学,现为硕士研究生,研究领域为液态熔盐堆热工水力学
  王纳秀,E-mail:wangnaxiu@sinap.ac.cn
- 基金信息：
- DOI：10.11889/j.0253-3219.2016.hjs.39.050601
  中图分类号： TL334
- 收稿日期：2016-02-22，
  
  录用日期：2016-03-23，
  
  纸质出版日期：2016-01-25
- 稿件说明：
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周振华, 潘登, 陈玉爽, 等. 一种液态燃料熔盐堆堆芯流量分配设计[J]. 核技术, 2016,39(5):050601

Zhenhua ZHOU, Deng PAN, Yushuang CHEN, et al. Core flow distribution design of molten salt reactor with liquid fuel[J]. Nuclear techniques, 2016, 39(5): 050601
周振华, 潘登, 陈玉爽, 等. 一种液态燃料熔盐堆堆芯流量分配设计[J]. 核技术, 2016,39(5):050601 DOI： 10.11889/j.0253-3219.2016.hjs.39.050601.

Zhenhua ZHOU, Deng PAN, Yushuang CHEN, et al. Core flow distribution design of molten salt reactor with liquid fuel[J]. Nuclear techniques, 2016, 39(5): 050601 DOI： 10.11889/j.0253-3219.2016.hjs.39.050601.

摘要

在液态燃料熔盐堆(Molten salt reactor

MSR)热工水力设计中

为实现堆芯径向功率展平需对堆芯流量分配进行设计

使得堆芯进口流量分布正比于释热量分布

而下腔室结构和流场分布对堆芯流量分配起决定性作用。利用FLUENT软件对堆芯三维流场进行模拟

通过调节下腔室结构和流量分配装置

对下腔室流场分布进行优化

最终实现堆芯流量合理分配。数值模拟结果表明

喇叭状下腔室比椭球形下腔室熔盐通道流量标准差降低4.2%

设置流量分配板熔盐通道流量标准差降低29.2%;改变下腔室结构和设置流量分配装置能够较好调节流量分配和功率分布匹配性

该结果可为液态熔盐堆堆芯优化设计提供依据。

Abstract

Background:

In the thermal-hydraulic design of molten salt reactor(MSR) with liquid fuel

the structure and the flow field distribution of lower plenum play a decisive role for the core flow distribution.

Purpose:

The mass flow distribution of core inlet is designed to match with the release heat distribution

so that the core power distribution will be flattened in radical.

Methods:

To realize the reasonable distribution of core flow

the flow field of lower plenum is optimized through adjusting the geometry of core lower plenum and flow distribution device using FLUENT software to simulate three-dimensional flow field of core.

Results:

The simulation results showed that the mass flow rate standard deviation of salt channels of trumpet-shape lower plenum is reduced by 4.2% compared with that of the ellipsoid-shape. The mass flow rate standard deviation of salt channel is reduced by 29.2% by setting the flow distribution plate.

Conclusion:

Changing the structure of lower plenum and setting the flow distribution plate are useful measures to adjust the mass flow distribution and power matching. The results can provide the basis fo

r the optimization design of MSR with liquid fuel.

关键词

Keywords

references

LeBlanc D . Molten salt reactors:a new beginning for an old idea . Nuclear Engineering and Design , 2010 . 240 1644 - 1656 .

Xu H J , Dai Z M , Cai X Z . Some physical issues of the thorium molten slat rector nuclear energy system . Nuclear Physics News , 2014 . 24 ( 2 ): 37 - 41 .

Yu C G , Li X X , Cai X Z , . Analysis of minor actinides transmutation for a molten salt fast reactor . Annals of Nuclear Energy , 2015 . 85 597 - 604 .

Bhatnagar V , Deffrennes M , Hugon M , . FISA-2009 conference on Euratom research and training activities: nuclear fission-past, present and future(Generation-Ⅱ, -Ⅲ and -IV+partitioning and transmutation) . Nuclear Engineering and Design , 2011 . 214 3376 - 3388 .

YANG Laisheng , SONG Guifang , HU Jun . Reactor hydraulic simulation test study of Qinshan phase -Ⅱ NNP project . Nuclear Power Engineering , 2003 . 24 ( S1 ): 208 - 211 .

杨来生 , 宋桂芳 , 胡俊 . 秦山核电二期工程反应堆水力模拟实验研究 . 核动力工程 , 2003 . 24 ( S1 ): 208 - 211 .

Botcher M , Krubmann R . Primary loop study of a VVER-1000 reactor with special focus on coolant mixing . Nuclear Engineering and Design , 2010 . 240 2244 - 2253 .

JIANG Mianheng , XU Hongjie , DAI Zhimin . Advanced fission energy program-TMSR nuclear energy system . Bulletin of Chinese Academy of Science , 2012 . 27 ( 3 ): 366 - 374 .

江绵恒 , 徐洪杰 , 戴志敏 . 未来先进核裂变能——TMSR核能系统 . 中国科学院院刊 , 2012 . 27 ( 3 ): 366 - 374 .

ZHANG Shuming , LI Huaqi , ZHAO Minfu , . Numerical analysis of flow distribution at the reactor core inlet of Qinshan Phase-Ⅱ reactor . Chinese Journal of Nuclear Science and Engineering , 2010 . 30 ( 4 ): 299 - 307 .

张曙明 , 李华奇 , 赵民富 , . 秦山核电站二期反应堆堆芯流量分配数值分析 . 核科学与工程 , 2010 . 30 ( 4 ): 299 - 307 .

DU Daiquan , ZENG Xiaokang , YANG Xiaoqiang , . CFD analysis of flow distribution of reactor core and temperature rise of coolant in fuel assembly for VVER reactor . Atomic Energy Science and Technology , 2015 . 49 ( 3 ): 429 - 432 .

杜代全 , 曾小康 , 杨晓强 , . VVER型反应堆堆芯流量分配与组件冷却剂温升CFD分析 . 原子能科学技术 , 2015 . 49 ( 3 ): 429 - 432 .

Youngmin Bae , Young In Kim , Cheon Tae Park . CFD analysis of flow distribution at the core inlet of SMART . Nuclear Engineering and Design , 2013 . 258 19 - 25 .

Zhou J J , Guo Z P , Qiu S Z , . The influence of lower plenum and distribution plates to thermal hydraulics characteristics of MSR . Nuclear Engineering and Design , 2013 . 256 235 - 248 .

WANG Xiaojun . Development and application of CFD in the nuclear industry I-situation and development trend of single-phase CFD method . Foreign Nuclear Power , 2005 . 26 ( 1 ): 2 - 6 .

王小军 . CFD的发展及其在核工业的应用I-单相CFD 方法的现状和发展趋势 . 国外核动力 , 2005 . 26 ( 1 ): 2 - 6 .

Reactor Physics Department . 2MW liquid fuel thorium-based molten salt reactor experimental reactor thermal hydraulic design report . TMSR Center of Excellence , 2014 . 5 - 6 .

反应堆物理部 . 2 MW液态燃料钍基熔盐堆实验堆热工水力设计报告 . TMSR卓越中心 , 2014 . 5 - 6 .

JIA Yunpeng , WANG Zihao , GENG Junxia , . Evaporation and separation of CsF in FLiNaK molten salt . Nuclear Techniques , 2016 . 39 ( 2 ): 020602 .

贾昀澎 , 王子豪 , 耿俊霞 , . FLiNaK熔盐中CsF的蒸发与分离 . 核技术 , 2016 . 39 ( 2 ): 020602 .

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