Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference34 articles.
1. Beall, S. E., Haubenreich, P. N., Lindauer, R. B., & Tallackson, J. R. (1964). MSRE design and operations report. part v. reactor safety analysis report (ORNL-TM-732, 4034157; p. ORNL-TM-732, 4034157). doi: 10.2172/4034157.
2. Betzler, B. (2021). Liquid-fueled molten salt reactor depletion modeling. Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States).
3. Blanes, S., Casas, F., & Murua, A. (2008). Splitting and composition methods in the numerical integration of differential equations. ArXiv Preprint ArXiv:0812.0377.
4. ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data;Chadwick;Nucl. Data Sheets,2011
5. DOENE (USDOE Office of Nuclear Energy, Science and Technology (NE)). (2002). A Technology Roadmap for Generation IV Nuclear Energy Systems (GIF-002-00, 859029; p. GIF-002-00, 859029). doi: 10.2172/859029.