Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components
Author:
Affiliation:
1. Argonne National Laboratory, Lemont, IL
2. RI Jetter Consulting, Pebble Beach, CA
Abstract
Publisher
American Society of Mechanical Engineers
Link
http://asmedigitalcollection.asme.org/PVP/proceedings-pdf/doi/10.1115/PVP2020-21493/6583152/v001t01a070-pvp2020-21493.pdf
Cited by 3 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献
1. A Study on Creep-Fatigue Evaluation of Nuclear Cladded Components by ASME-III Division 5;Energies;2023-03-21
2. Designing Cladded Components for High Temperature Nuclear Service: Part I—Analysis Methods;Journal of Pressure Vessel Technology;2022-12-02
3. Designing Cladded Components for High Temperature Nuclear Service: Part II—Design Rules;Journal of Pressure Vessel Technology;2022-12-02
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