UCO - TRISO核组成的热化学界

IF 3.3 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 Epub Date: 2024-11-29 DOI:10.1016/j.jnucmat.2024.155537
M. Poschmann, D. Wojtaszek, E. Geiger
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引用次数: 0

摘要

通过非常详细的平衡热力学计算,得出了安全新鲜UCO TRISO燃料核化学的边界,即UCx的分数。选择UCx的下界是为了限制CO压力,选择上界是为了保证关注的放射性核素裂变和嬗变产物的氧化。可以根据目标燃耗和燃料温度计算边界。与AGR-2实验相似的演示燃料设计的计算边界与先前计算的下界和用于确定上界的实验证据很好地吻合,并表明参考燃料设计,如AGR-2和MHTGR-350,即使燃耗高达21.3% FIMA,也完全在安全成分区域内。对铯、钯、银、钡、锶和锆的预测形态进行了研究,并为相关系统的热力学评估提供了建议。
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Thermochemical bounds on UCO TRISO kernel compositions
Highly-detailed equilibrium thermodynamics calculations were used to derive bounds on safe fresh UCO TRISO fuel kernel chemistries, in terms of the fraction of UCx. The lower bound on UCx was chosen to limit CO pressure, and the upper bound to ensure oxidation of radionuclide fission and transmutation products of concern. The bounds can be calculated with respect to both target burnup and fuel temperature. Calculated bounds for a demonstration fuel design similar to the AGR-2 experiment are in good agreement with previously-calculated lower bounds and experimental evidence used to determine upper bounds, and indicate that reference fuel designs such as AGR-2 and MHTGR-350 are well-within the safe composition region even for burnup as high as 21.3% FIMA. Predicted speciations of cesium, palladium, silver, barium, strontium, and zirconium were examined, and recommendations for thermodynamic assessments of relevant systems provided.
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来源期刊
Journal of Nuclear Materials
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.
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