Microstructure response and sodium corrosion behavior of ferritic-martensitic steel after proton irradiation

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Technology Pub Date : 2024-12-01 Epub Date: 2024-07-06 DOI:10.1016/j.net.2024.07.011
Jeonghyeon Lee , Taeho Kim , Taeyong Kim , Ji Hyun Kim
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Abstract

In nuclear reactors, cladding materials are irradiated by neutrons as well as various types of ion beams that can induce radiation damage. Proton irradiation has been used for the past few decades to simulate neutron damage because protons have a higher scattering cross-section than fast neutrons and can effectively form displacements. This study is aimed at investigating the irradiation effects on the corrosion behavior of FMS. Non-irradiated and irradiated FMS materials were used for corrosion and dissolution experiments in a liquid sodium environment. It was observed that the irradiated materials exhibited worse corrosion and dissolution than the non-irradiated materials.
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质子辐照后铁素体-马氏体钢的显微结构响应和钠腐蚀行为
在核反应堆中,包壳材料会受到中子以及各种离子束的辐照,从而诱发辐射损伤。过去几十年来,质子辐照一直被用于模拟中子损伤,因为质子的散射截面比快中子高,能有效地形成位移。本研究旨在研究辐照对 FMS 腐蚀行为的影响。在液态钠环境中,使用未经辐照和经过辐照的 FMS 材料进行腐蚀和溶解实验。结果表明,与未受辐照的材料相比,受辐照的材料表现出更差的腐蚀性和溶解性。
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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