将BISON与数据库集成，实现金属燃料瞬态燃料包层界面液化模型评估平台

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-09-22 DOI:10.1016/j.jnucmat.2025.156168

Yinbin Miao , Shipeng Shu , Aaron Oaks , Carolyn Tomchik , Kun Mo , Christopher Matthews , Adam Zabriskie , Stephen Novascone , Abdellatif M. Yacout

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引用次数: 0

摘要

在BISON燃料性能规范中，开发了一个新的平台来评估钠冷快堆（SFR）金属燃料的燃料包壳界面液化模型。该平台至关重要，因为燃料包层界面的液化会显著影响燃料性能，并可能在瞬态事件中损害燃料销的完整性。为了确保准确的预测，该平台整合了在整体快堆（IFR）项目期间收集的数据，这些数据目前已存档在金属燃料数据库中。该集成支持BISON中模型的验证和确认（V&；V）。利用美国在金属燃料液化方面的丰富经验和保存的遗留数据，该平台可作为评估现有模型和推进新模型开发的强大工具。

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Metallic fuel transient fuel-cladding interface liquefaction model assessment platform enabled by integrating BISON with databases

A novel platform has been developed within the BISON fuel performance code to assess models of fuel-cladding interface liquefaction for sodium-cooled fast reactor (SFR) metallic fuels. This platform is crucial because liquefaction at the fuel-cladding interface significantly impacts fuel performance and may compromise fuel pin integrity during transient events. To ensure accurate predictions, the platform integrates data collected during the Integral Fast Reactor (IFR) program, now archived in metallic fuel databases. This integration supports verification and validation (V&V) of the models in BISON. Leveraging the extensive US experience with metallic fuel liquefaction and the collections of preserved legacy data, the platform serves as a powerful tool for evaluating existing models and advancing the development of new ones.

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.