Experimental study on the oxidation behavior of nuclear graphite IG-110

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-02-22 DOI:10.1016/j.jnucmat.2025.155712

Bin Lin , Liang Chen , Guisen Liu , Yao Shen

引用次数: 0

Abstract

This study presents an experimental investigation on the oxidation behavior of nuclear graphite IG-110. A gas chromatography-based oxidation test platform was developed to monitor the oxidation processes of IG-110 graphite in different atmospheres. The oxidation tests focused on the presence of H₂O and O₂, with temperatures up to 750 °C and various partial pressures. The graphite consumption was analyzed, and a Boltzmann function was proposed to describe the relationship between graphite consumption and oxygen partial pressure. A graphite consumption prediction model was developed based on this function, which can be utilized to calculate the graphite consumption of CO/CO₂ reaction products in High-Temperature Gas-cooled Reactors (HTGRs).

查看原文本刊更多论文

求助全文

约1分钟内获得全文求助全文

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.