Aerosol behavior model development and validation of SPRUCE code source term module

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

Annals of Nuclear Energy Pub Date : 2026-08-01 Epub Date: 2026-03-11 DOI:10.1016/j.anucene.2026.112262

Pingwen Ou , Peng Chen , Yong Ouyang , Chao Guo , Meilan Chen , Dongyu He , Yongzheng Chen

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引用次数: 0

Abstract

The aerosol behavior plays an important role in the assessment of the source term during severe accidents in nuclear power plants. This paper presents the development and validation of the aerosol behavior model within the source term module of the SPRUCE code, an integral severe accident analysis code independently developed by the China Nuclear Power Technology Research Institute (CNPRI). The model comprehensively incorporates the key physical processes governing aerosol behavior, including deposition (gravitational settling, thermophoresis, diffusiophoresis, and Brownian diffusion), coagulation (Brownian, gravitational, and turbulent), hygroscopic growth, and resuspension. To validate the reliability of model, simulations were compared against the internationally recognized experimental data, including the LACE LA4, KAEVER (K123, K148, K186, K188), and STORM SR11. The results demonstrate that the SPRUCE code successfully predicts the temporal evolution of aerosol concentration and deposition/resuspension behavior in various thermal–hydraulic conditions and aerosol types (soluble, insoluble, and mixed). The favorable agreement with experimental data confirms the capability and credibility of the SPRUCE code and its implemented aerosol models for simulating aerosol behavior under severe accident conditions. This work establishes a solid foundation for the application of SPRUCE in severe accident source term analysis, paving the way for future validation of other critical source term phenomena and other modules of SPRUCE.

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气溶胶行为模型开发与验证的SPRUCE代码源项模块

在核电站重大事故的源项评价中，气溶胶的行为起着重要的作用。本文介绍了中国核电技术研究院自主开发的严重事故综合分析规范SPRUCE源项模块中气溶胶行为模型的开发与验证。该模型综合了控制气溶胶行为的关键物理过程，包括沉积（重力沉降、热泳进、扩散泳进和布朗扩散）、凝聚（布朗、重力和湍流）、吸湿生长和再悬浮。为了验证模型的可靠性，将模拟结果与LACE LA4、KAEVER （K123、K148、K186、K188）和STORM SR11等国际公认的实验数据进行了比较。结果表明，SPRUCE程序成功地预测了不同热水力条件和气溶胶类型（可溶性、不溶性和混合）下气溶胶浓度和沉积/再悬浮行为的时间演变。与实验数据的良好一致性证实了SPRUCE规范及其实现的气溶胶模型在严重事故条件下模拟气溶胶行为的能力和可信度。本工作为SPRUCE在严重事故源项分析中的应用奠定了坚实的基础，为未来验证其他关键源项现象和SPRUCE的其他模块铺平了道路。

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.