基于氧化腐蚀特性的铅铋堆单棒核-热-材耦合研究

季旭; 柴翔; 张乐福; 刘晓晶

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基于氧化腐蚀特性的铅铋堆单棒核-热-材耦合研究

更新时间：2024-11-27

- 基于氧化腐蚀特性的铅铋堆单棒核-热-材耦合研究
- Neutronics -thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics
- 核技术 2024年文章编号：XXXXXX
- 作者机构：
  
  上海交通大学核科学与工程学院上海200240
- 作者简介：
  
  季旭，男，1999年出生，2021年毕业于哈尔滨工程大学，现为硕士研究生，研究领域为核反应堆多物理场耦合
  刘晓晶，E-mail：xiaojingliu@sjtu.edu.cn
- 基金信息：
  
  上海市2020年度技术带头人项目(20XD1434100)
- DOI：
  中图分类号： TL99
- 网络出版日期：2024-11-27，
  
  收稿日期：2023-11-29，
  
  修回日期：2024-04-25，
- 稿件说明：
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季旭, 柴翔, 张乐福, 等. 基于氧化腐蚀特性的铅铋堆单棒核-热-材耦合研究[J/OL]. 核技术, 2024,XXXXXX

JI Xu, CHAI Xiang, ZHANG Lefu, et al. Neutronics -thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics. [J/OL]. NUCLEAR TECHNIQUES, 2024,XXXXXX
季旭, 柴翔, 张乐福, 等. 基于氧化腐蚀特性的铅铋堆单棒核-热-材耦合研究[J/OL]. 核技术, 2024,XXXXXX DOI：

JI Xu, CHAI Xiang, ZHANG Lefu, et al. Neutronics -thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics. [J/OL]. NUCLEAR TECHNIQUES, 2024,XXXXXX DOI：

摘要

铅铋堆的氧化腐蚀受温度、氧浓度、时间等多因素影响，同时氧化层的生长也改变了堆芯热工水力和中子物理参数，因此，研究铅铋堆的氧化腐蚀场、热工水力场和中子物理场的耦合作用对铅铋堆应用有重要意义。本工作基于面向对象的多物理场仿真环境（Multiphysics Object-Ori1ented Simulation Environment，MOOSE）搭建了核-热-材多物理场耦合框架，开展了单棒在基准工况下的核-热-材耦合分析，并研究了氧浓度对关键耦合参数的影响。结果表明：基准工况下氧化腐蚀10 000 h后氧化层平均厚度约为10 μm，燃料最大温升为16 K，

inf

下降10

-4

；氧浓度升高可以极有效地抑制磁铁矿溶解，但是对Fe-Cr尖晶石生长的促进作用较小。

Abstract

Background

Liquid lead-bismuth eutectic (LBE) corrosion and dissolution of structural materials pose significant challenges in the application of lead-bismuth-cooled fast reactors (LFRs). The use of oxygen as an inhibitor emerges as a promising approach to mitigate the corrosion of structural materials by liquid LBE. The oxidative corrosion in LFRs is influenced by various physical parameters within the reactor

including temperature

oxygen concentration

and time. Concurrently

the growth of the oxide layer on the cladding surface exacerbates the heat transfer between the cladding and the coolant

thereby influencing the thermal-hydraulic and neutron physics parameters of the core. Understanding the corrosion protection of structural materials and multi-physics characteristics is crucial issue for LFRs.

Purpose

This study aims to investigate the coupled mechanisms of neutron physics

thermal-hydraulics

and oxidative corrosion

along with the distribution of the oxide layer in lead-bismuth reactors.

Methods

A neutronics-thermal-hydraulics-material coupling framework was developed to investigate the variations in multi-physics parameters and oxide layer distribution in the LFR fuel rod under oxidative corrosion conditions. First of all

based on the Multiphysics Object-Oriented Simulation Environment (MOOSE)

the framework was developed to couple three modules: neutron physics

thermal-hydraulics

and oxidative corrosion

and conduct simulation calculations. Thereafter

various lead-bismuth reactor oxide layer growth-removal models were encompassed into a MOOSE-based oxidative corrosion module

named Seal

and the Martinelli model was adopted in subsequent simulations after comparison with experimental values. Then

the neutron physics module was solved by the open-source neutron diffusion equation solver Moltres and the thermal-hydraulics module calculation was performed by MOOSE's Navier-Stokes and Heat Conduction modules. Two coupling relationships in the coupling framework

i.e.

(1) the neutron physics module for transferring power distribution to the thermal-hydraulics module

and the thermal-hydraulics module transferring temperature distribution to the neutron physics module; (2) the thermal-hydraulics module transferring temperature field and flow field to the oxidative corrosion module

and the oxidative corrosion module transferring oxide layer thickness distribution to the thermal-hydraulics module

were investigated. Finally

the approach of simultaneously solving the coupled equations under the same mesh was employed for coupled calculations

with the control equations of the three modules solved simultaneously to achieve synchronized convergence of physical quantities. And the developed coupled framework was applied to perform benchmark calculations and sensitivity analysis of oxygen concentration for a lead-bismuth reactor fuel rod.

Results

The results indicate that: (1) after 10 000 h of oxidative corrosion under benchmark conditions

the average thickness of the oxide layer is approximately 10 μm

the maximum fuel temperature rise is 16 K

and keff decreases by 10

-4

; (2) an increase in oxygen concentration effectively inhibits magnetite dissolution but has a relatively minor promoting effect on the growth of Fe-Cr spinel.

Conclusions

This study demonstrates that the increase in oxygen concentration has a positive effect on the protection and self-healing ability of the oxide layer. It has both theoretical and practical significance for the development

design

and safety evaluation of LFR in China.

关键词

核-热-材耦合氧化腐蚀铅铋堆面向对象的多物理场仿真环境

Keywords

Neutronics -Thermal-Hydraulics-Material couplingOxidation corrosionLead-Bismuth cooled reactorMultiphysics object-oriented simulation environment (MOOSE)

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