Numerical study of lead oxide precipitation in liquid lead–bismuth eutectic

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-09-17 DOI:10.1016/j.anucene.2025.111885

Jinye Luo , Maolong Liu , Xianglong Guo

引用次数: 0

Abstract

Liquid lead–bismuth eutectic (LBE) is considered a promising primary coolant for Generation IV nuclear fast reactors. However, the ingress of oxygen into LBE cooled reactors can cause lead oxide (PbO) precipitation. In order to evaluate the safety in the presence of PbO, quantification study of PbO precipitation in LBE cooled reactor especially in heat exchangers is necessary while insufficient study is currently unveiled. In this study, the nucleation, growth and dissolution of PbO are concerned. The population balance model is applied to characterize the distribution of particle sizes. With the use of CFD code ANSYS FLUENT, the simulation model was validated using the existing data. Then, the model was applied to the calculations of Printed Circuit Heat Exchanger (PCHE). The amount and location of PbO precipitates in PCHE under various conditions were calculated. The numerical simulation results are useful to improve the safety and performance of LBE cooled reactors.

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铅铋共晶液中氧化铅析出的数值研究

液态铅铋共晶（LBE）被认为是一种很有前途的第四代快堆主冷剂。然而，氧气进入LBE冷却反应堆会导致氧化铅（PbO）的沉淀。为了评价PbO存在时的安全性，有必要对LBE冷却堆特别是换热器中PbO的沉淀进行定量研究，但目前研究不足。本文研究了PbO的成核、生长和溶解。采用种群平衡模型来描述颗粒大小的分布。利用CFD软件ANSYS FLUENT，利用已有数据对仿真模型进行了验证。然后，将该模型应用于印刷电路换热器（PCHE）的计算。计算了不同条件下PbO在PCHE中的析出量和位置。数值模拟结果对提高LBE冷却堆的安全性和性能具有指导意义。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.