Author:
Stempien John D.,Ballinger Ronald G.,Forsberg Charles W.
Funder
Department of Energy (DOE) Nuclear Energy University Program (NEUP)
University of Wisconsin-Madison
Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference67 articles.
1. Fatigue crack initiation in Hastelloy X – the role of boundaries;Abuzaid;Fatigue Fract Eng. Mater. Struct.,2013
2. Deuterium/tritium behavior in Flibe and Flibe-facing materials;Anderl;J. Nucl. Mater.,2004
3. Technical Description of the “Mark 1” Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant (No. UCBTH-14-002);Andreades,2014
4. Analysis of corrosion of stainless steel in a sodium and high radiation environment;Anno;Nucl. Technol.,1971
5. Absorption and desorption of deuterium on graphite at elevated temperatures;Atsumi;J. Nucl. Mater.,1988
Cited by
39 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