Numerical study on flow and heat transfer characteristics of helical fuel in lead-bismuth reactor

JIANG Dianqiang; DENG Jian; ZHANG Dalin; LU Qi; ZHANG Ting; WU Xiaoli; TIAN Wenxi

doi:10.3724/j.0253-3219.2025.hjs.48.240360

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Numerical study on flow and heat transfer characteristics of helical fuel in lead-bismuth reactor

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2025-11-27

- Numerical study on flow and heat transfer characteristics of helical fuel in lead-bismuth reactor
- NUCLEAR TECHNIQUES Vol. 48, Issue 11, Article number: 110604(2025)
- 作者机构：
  
  1.西安交通大学核科学与技术学院西安 710049
  2.中国核动力研究设计院成都 610213
- 作者简介：
  
  JIANG Dianqiang, male, born in 1998, graduated from Harbin Engineering University in 2020, doctoral student, focusing on the thermal-hydraulic characteristics of nuclear reactors
  ZHANG Dalin, E-mail: dlzhang@mail.xjtu.edu.cn
- 基金信息：
  
  Plan Project of Science and Technology Department of Sichuan Province(2022JDJQ0002);National Natural Science Foundation of China(12275261)
- DOI：10.3724/j.0253-3219.2025.hjs.48.240360
  CLC： TL334
- Received：09 September 2024，
  
  Revised：2025-10-24，
  
  Published：15 November 2025
- 稿件说明：
移动端阅览
姜殿强,邓坚,张大林等.铅铋堆螺旋形燃料流动传热特性数值研究[J].核技术,2025,48(11):110604.

JIANG Dianqiang,DENG Jian,ZHANG Dalin,et al.Numerical study on flow and heat transfer characteristics of helical fuel in lead-bismuth reactor[J].NUCLEAR TECHNIQUES,2025,48(11):110604.
姜殿强,邓坚,张大林等.铅铋堆螺旋形燃料流动传热特性数值研究[J].核技术,2025,48(11):110604. DOI： 10.3724/j.0253-3219.2025.hjs.48.240360. CSTR： 32193.14.hjs.CN31-1342/TL.2025.48.240360.

JIANG Dianqiang,DENG Jian,ZHANG Dalin,et al.Numerical study on flow and heat transfer characteristics of helical fuel in lead-bismuth reactor[J].NUCLEAR TECHNIQUES,2025,48(11):110604. DOI： 10.3724/j.0253-3219.2025.hjs.48.240360. CSTR： 32193.14.hjs.CN31-1342/TL.2025.48.240360.

摘要

为研究铅铋堆螺旋形燃料流动阻力、对流传热及横向搅混特性，评估不同形式螺旋形燃料的综合流动传热性能。采用计算流体力学方法对比分析不同形式2×2螺旋形燃料的阻力系数

、

及综合性能评价因子，评估其流动传热特性。对比分析不同形式3×3螺旋形燃料棒束的流动后掠搅混参数及截面温度分布，评估其横向搅混特性。采用综合性能评价因子评估三种螺旋形燃料综合流动传热性能。结果表明：1）螺旋形燃料综合性能取决于叶瓣与叶谷半径之比，该比值越大，其性能越差；2）典型四瓣螺旋形燃料对流传热性能优于另外两种六瓣螺旋形燃料；3）大瓣谷径比六瓣螺旋形燃料具有更大的内/内通道交界面流动后掠搅混参数，且截面子通道温度分布更均匀。最后，通过雷达图得出四瓣螺旋形燃料更适合作为铅铋堆优选核燃料。

Abstract

Background

The Lead-Bismuth-cooled fast Reactor (LBR) is one of the advanced Generation IV nuclear energy systems. The majority of the LBR concept design uses wire-wrapped fuel assembly. The helical fuel

a new type of nuclear fuel

can be used in potential LBR

which can enable fuel self-supporting of and improve heat transfer.

Purpose

This study aims to study the flow resistance

convective heat transfer

and transverse mixing characteristics of helical fuels in LBR and evaluate the comprehensive flow and heat transfer performance of different helical fuels.

Methods

The Computational Fluid Dynamics (CFD) was employed in this study to compare the resistance coefficient (

)

Nusselt number (

)

and comprehensive performance evaluation factors of various 2×2 helical fuel bundles

thereby assessing their flow and heat transfer cha

racteristics. Additionally

the flow sweep mixing parameters and temperature distribution of a 3×3 helical fuel bundles were analyzed to evaluate the transverse mixing characteristics. Furthermore

the comprehensive performance evaluation factors of three types of helical fuel bundles were compared to assess their overall flow and heat transfer performance.

Results

The results demonstrate the following key findings: 1) The comprehensive performance of helical fuels is significantly influenced by the blade-to-valley radius ratio. Specifically

an increase in this ratio leads to a degradation in overall performance. 2) Among the helical fuel configurations examined

the four-blade helical fuel exhibits superior convective heat transfer performance. 3) When comparing the flow sweep mixing parameters across the three types of helical fuels

it is observed that the flow sweep mixing parameters at the inner/inner subchannel interface are larger for helical fuels with a higher blade-to-valley radius ratio. This condition also results in a more uniform temperature distribution across different subchannels.

Conclusions

The results of this study show that the four-blade helical fuel is more suitable as the preferred nuclear fuel for the lead-bismuth reactor.

关键词

Keywords

references

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