KRUSTY堆芯保温层对功率的影响

张洁; 刘福东; 王昆鹏

doi:10.3724/j.0253-3219.2026.hjs.49.240517

您当前的位置：

首页 >

文章列表页 >

KRUSTY堆芯保温层对功率的影响

核能科学与工程 | 更新时间：2026-01-19

- KRUSTY堆芯保温层对功率的影响
- The effect of insulation layer of KRUSTY on reactor power
- 核技术 2026年49卷第1期文章编号：010607
- 作者机构：
  
  1.生态环境部核与辐射安全中心北京 102401
  2.国家环境保护核与辐射安全审评模拟分析与验证重点实验室北京 102401
  3.上海交通大学机械与动力工程学院上海 200240
- 作者简介：
  
  张洁，男，1982年出生，2019年于中国科学院大学获博士学位，研究领域为反应堆热工水力
  刘福东，E-mail：liufudong1968@sina.com
- 基金信息：
  
  国家自然科学基金(12435012)
- DOI：10.3724/j.0253-3219.2026.hjs.49.240517
  中图分类号： TL333
- 收稿：2024-12-30，
  
  修回：2025-06-19，
  
  纸质出版：2026-01-15
- 稿件说明：
移动端阅览
张洁,刘福东,王昆鹏.KRUSTY堆芯保温层对功率的影响[J].核技术,2026,49(01):010607.

ZHANG Jie,LIU Fudong,WANG Kunpeng.The effect of insulation layer of KRUSTY on reactor power[J].NUCLEAR TECHNIQUES,2026,49(01):010607.
张洁,刘福东,王昆鹏.KRUSTY堆芯保温层对功率的影响[J].核技术,2026,49(01):010607. DOI： 10.3724/j.0253-3219.2026.hjs.49.240517. CSTR： 32193.14.hjs.CN31-1342/TL.2026.49.240517.

ZHANG Jie,LIU Fudong,WANG Kunpeng.The effect of insulation layer of KRUSTY on reactor power[J].NUCLEAR TECHNIQUES,2026,49(01):010607. DOI： 10.3724/j.0253-3219.2026.hjs.49.240517. CSTR： 32193.14.hjs.CN31-1342/TL.2026.49.240517.

摘要

热管堆属于小型模块化反应堆，具有结构简单、建造方便、易于部署等特点，其运行于负荷跟踪模式。KRUST

Y（Kilowatt Reactor Using Stirling TechnologY）作为热管堆Kilopower的原型机，已经经过了相关测试并取得了令人满意的结果。为了进一步优化KRUSTY的结构，深入理解保温层对反应堆的影响，提升反应堆输出能量的效率，特此对其展开研究。通过多物理场软件Simscape对KRUSTY进行建模，并根据模型进行6种不同程度的修改方案，计算了0.6 $反应性启动、±4×10

-4

反应性引入以及±50%负荷改变工况下各个方案的反应堆行为。其中，多层保温材料（Multilayer Insulation，MLI）加倍方案的能量输出效率最高，达到了79.71%。结果表明：在堆芯、真空罐、反射层等结构间增加空隙数量，并且真空罐内部含有较厚保温层的情况下，反应堆导出能量的效率更高。

Abstract

Background

Small modular reactor has the characteristics of simple structure

convenient construction and easy deployment. As a type of small modular reactor

the heat pipe reactor is usually operated in load following mode. Kilopower is a typical heat pipe reactor designed to provide 1 kW to 10 kW of electricity in space or on the surface of a planet or moon. As the prototype of the heat pipe reactor

the Kilowatt Reactor Using Stirling TechnologY (KRUSTY) has been tested and achieved satisfactory results.

Purpose

This study aims to optimize the structure of KRUSTY

understand the influence of insulation layer on the reactor

and improve the efficiency of reactor output energy.

Methods

Firstly

the multi-physics software Simscape was used as the system analysis tool

and the reactor power calculation module

heat pipe module and so on were added for the simulation of heat pipe reactor. Secondly

taking KURSTY as the object

the system models with six different insulation thickness schemes were built. Finally

the reactor behaviors under the conditions of 0.6 $ reactivity startup

±4×10

-4

reactivity introduction and ±50% load change were investiged

and the calculation results under different schemes were compared.

Results

Comparison results show that the energy output efficiency of double thickness of Multilayer Insulation (MLI) scheme is the highest

reaching 79.71% with minimal the influence of each working condition on the energy output efficiency.

Conclusions

The results show that the efficiency of the reactor's energy output is higher when the number of gaps is increased between the core

the vacuum tank

the neutron reflector and other structures

and the vacuum tank contains a thick insulation layer.

关键词

Keywords

references

McClure P R , Poston D I , Gibson M A , et al . Kilopower project: the KRUSTY fission power experiment and potential missions [J ] . Nuclear Technology , 2020 , 206 ( sup1 ): S1 – S12 . DOI: 10.1080/00295450.2020.1722554 http://dx.doi.org/10.1080/00295450.2020.1722554 .

王傲 , 申凤阳 , 胡古 , 等 . 热管空间核反应堆电源的研究进展 [J ] . 核技术 , 2020 , 43 ( 6 ): 060002 . DOI: 10.11889/j.0253-3219.2020.hjs.43.060002 http://dx.doi.org/10.11889/j.0253-3219.2020.hjs.43.060002 .

WANG Ao , SHEN Fengyang , HU Gu , et al . A survey of heatpipe space nuclear reactor power supply [J ] . Nuclear Techniques , 2020 , 43 ( 6 ): 060002 . DOI: 10.11889/j.0253-3219.2020.hjs.43.060002 http://dx.doi.org/10.11889/j.0253-3219.2020.hjs.43.060002 .

Poston D I , Gibson M A , Sanchez R G , et al . Results of the KRUSTY nuclear system test [J ] . Nuclear Technology , 2020 , 206 ( sup1 ): S89 – S117 . DOI: 10.1080/00295450. 2020.1730673 http://dx.doi.org/10.1080/00295450.2020.1730673 .

汪镇澜 , 苟军利 , 徐世浩 , 等 . 新型兆瓦级热管堆热管失效事故分析 [J ] . 核技术 , 2022 , 45 ( 11 ): 110604 . DOI: 10.11889/j.0253-3219.2022.hjs.45.110604 http://dx.doi.org/10.11889/j.0253-3219.2022.hjs.45.110604 .

WANG Zhenlan , GOU Junli , XU Shihao , et al . Heat pipe failure accident analysis of a new type of megawatt heat pipe reactor [J ] . Nuclear Techniques , 2022 , 45 ( 11 ): 110604 . DOI: 10.11889/j.0253-3219.2022.hjs.45.110604 http://dx.doi.org/10.11889/j.0253-3219.2022.hjs.45.110604 .

杨轩 , 李权 , 李晨曦 , 等 . 热管堆固态堆芯燃料辐照-热-力耦合性能分析 [J ] . 核技术 , 2024 , 47 ( 7 ): 070601 . DOI: 10.11889/j.0253-3219.2024.hjs.47.070601 http://dx.doi.org/10.11889/j.0253-3219.2024.hjs.47.070601 .

YANG Xuan , LI Quan , LI Chenxi , et al . Coupled irradiation-thermal-mechanical analysis of fuel in solid core of heat pipe cooled reactor [J ] . Nuclear Techniques , 2024 , 47 ( 7 ): 070601 . DOI: 10.11889/j.0253-3219.2024.hjs.47.070601 http://dx.doi.org/10.11889/j.0253-3219.2024.hjs.47.070601 .

Poston D I , Gibson M A , Godfroy T , et al . KRUSTY reactor design [J ] . Nuclear Technology , 2020 , 206 ( sup1 ): S13 – S30 . DOI: 10.1080/00295450.2020.1725382 http://dx.doi.org/10.1080/00295450.2020.1725382 .

Wilson S . Overview of stirling technology research at NASA Glenn research center [C ] // 13th International Energy Conversion Engineering Conference . Orlando, FL. AIAA , 2015 : AIAA2015-3905. DOI: 10.2514/6.2015-3905 http://dx.doi.org/10.2514/6.2015-3905 .

堵树宏 , 李永华 , 孙涛 , 等 . 微型核反应堆技术发展趋势研究 [J ] . 核动力工程 , 2022 , 43 ( 4 ): 1 – 4 . DOI: 10.13832/j.jnpe.2022.04.0001 http://dx.doi.org/10.13832/j.jnpe.2022.04.0001 .

DU Shuhong , LI Yonghua , SUN Tao , et al . Research on the development trend of micro nuclear reactor technology [J ] . Nuclear Power Engineering , 2022 , 43 ( 4 ): 1 – 4 . DOI: 10.13832/j.jnpe.2022.04.0001 http://dx.doi.org/10.13832/j.jnpe.2022.04.0001 .

Cao Y , Faghri A . A numerical analysis of high-temperature heat pipe startup from the frozen state [J ] . Journal of Heat Transfer , 1993 , 115 ( 1 ): 247 – 254 . DOI: 10.1115/1.2910657 http://dx.doi.org/10.1115/1.2910657 .

沈妍 , 张红 , 许辉 , 等 . 组合式吸液芯高温热管热阻和瞬时传热性能分析 [J ] . 应用基础与工程科学学报 , 2015 , 23 ( 3 ): 541 – 553 . DOI: 10.16058/j.issn.1005-0930.2015.03.013 http://dx.doi.org/10.16058/j.issn.1005-0930.2015.03.013 .

SHEN Yan , ZHANG Hong , XU Hui , et al . Analysis on transient heat transfer performance and thermal resistances of high temperature heat pipe with combined wick [J ] . Journal of Basic Science and Engineering , 2015 , 23 ( 3 ): 541 – 553 . DOI: 10.16058/j.issn.1005-0930.2015.03.013 http://dx.doi.org/10.16058/j.issn.1005-0930.2015.03.013 .

冯踏青 . 液态金属高温热管的理论和试验研究 [D ] . 杭州 : 浙江大学 , 1998 .

FENG Taqing . Theoretical and experimental study on liquid metal high temperature heat pipe [D ] . Hangzhou : Zhejiang University , 1998 .

吴攀 , 欧阳泽宇 , 朱煜 , 等 . 基于KRUSTY带核实验的热管冷却反应堆瞬态分析程序验证 [J ] . 核技术 , 2023 , 46 ( 11 ): 110603 . DOI: 10.11889/j.0253-3219.2023.hjs.46.110603 http://dx.doi.org/10.11889/j.0253-3219.2023.hjs.46.110603 .

WU Pan , OUYANG Zeyu , ZHU Yu , et al . Validation of an in-house system analysis code for heat pipe cooled reactor [J ] . Nuclear Techniques , 2023 , 46 ( 11 ): 110603 . DOI: 10.11889/j.0253-3219.2023.hjs.46.110603 http://dx.doi.org/10.11889/j.0253-3219.2023.hjs.46.110603 .

Ma Y G , Tian C Q , Yu H X , et al . Transient heat pipe failure accident analysis of a megawatt heat pipe cooled reactor [J ] . Progress in Nuclear Energy , 2021 , 140 : 103904 . DOI: 10.1016/j.pnucene.2021.103904 http://dx.doi.org/10.1016/j.pnucene.2021.103904 .

Yang S D , Feng W P , Ma Y G , et al . Study on the operating characteristics of Stirling engine based on an optimized analysis method [J ] . Nuclear Science and Techniques , 2025 , 36 ( 9 ): 161 . DOI: 10.1007/s41365-02501711-6 http://dx.doi.org/10.1007/s41365-02501711-6 .

Grove T , Hayes D , Goda J , et al . Kilowatt reactor using stirling TechnologY (KRUSTY) cold critical measurements [J ] . Nuclear Technology , 2020 , 206 ( sup1 ): S68 – S77 . DOI: 10.1080/00295450.2020.1712950 http://dx.doi.org/10.1080/00295450.2020.1712950 .

Poston D I , Gibson M A , McClure P R , et al . Results of the KRUSTY warm critical experiments [J ] . Nuclear Technology , 2020 , 206 ( sup1 ): S78 – S88 . DOI: 10.1080/00295450.2020.1727287 http://dx.doi.org/10.1080/00295450.2020.1727287 .

Gibson M A , Poston D I , McClure P R , et al . Heat transport and power conversion of the kilopower reactor test [J ] . Nuclear Technology , 2020 , 206 ( sup1 ): 31 – 42 . DOI: 10.1080/00295450.2019.1709364 http://dx.doi.org/10.1080/00295450.2019.1709364 .

浏览量

下载量

CSCD

文章被引用时，请邮件提醒。

提交

工具集

关联资源

KRUSTY反应堆系统运行瞬态分析

不同热电转换系统的热管堆反应性引入事故特性研究

乏燃料溶液系统临界安全分析计算方法研究

新型兆瓦级热管堆热管失效事故分析