Preliminary development and validation of ACENA code for melting and freezing behavior simulation

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-11-16 DOI:10.1016/j.anucene.2024.111049

Yue Lin , Dalin Zhang , Yutong Chen , Xisi Zhang , Jian Deng , Wenxi Tian , Suizheng Qiu , Guanghui Su

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Abstract

Melting and freezing model plays a crucial role in safety analysis for liquid metal fast reactors under core disruptive accidents. It’s necessary to establish suitable models for accurate prediction of molten materials migration after severe accidents happens. In this study, a kind of melting and freezing model is established in ACENA code. And the ACENA code is used to simulate the freezing behavior of melt and calculated results are compared with experimental results to validate the applicability of the model. According to the comparison it is shown that the simulation results by ACENA code agree well with experimental results. Both the changing trend and final value of penetration depth of melt are consistent with realistic conditions. Besides, the effects of heat exchange on penetration depth are also analyzed. This research contributes to the development of safety analysis tools for liquid metal reactors under severe accidents.

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初步开发和验证用于熔化和冻结行为模拟的 ACENA 代码

熔融和冻结模型在堆芯破坏事故下的液态金属快堆安全分析中起着至关重要的作用。有必要建立合适的模型，以准确预测严重事故发生后熔融材料的迁移。本研究在 ACENA 代码中建立了一种熔融和冻结模型。使用 ACENA 代码模拟熔体的冻结行为，并将计算结果与实验结果进行比较，以验证模型的适用性。比较结果表明，ACENA 代码的模拟结果与实验结果非常吻合。熔体渗透深度的变化趋势和最终值都符合实际情况。此外，还分析了热交换对渗透深度的影响。这项研究有助于开发严重事故下液态金属反应堆的安全分析工具。

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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.