Author:
Brown Nicholas R.,Betzler Benjamin R.,Carbajo Juan J.,Wysocki Aaron J.,Greenwood M. Scott,Gentry Cole,Qualls A. Louis
Funder
U.S. Department of Energy
DOE-NE
Georgia Institute of Technology
Subject
Nuclear Energy and Engineering
Reference28 articles.
1. “Evaluation of the LS-VHTR Concept”, AREVA NP Inc. under BEA Contract No. 00045559;AREVA NP Inc.,2007
2. Status of the NGNP fuel experiment AGR-2 irradiated in the advanced test reactor;Blaine Grover;Nucl. Eng. Des.,2014
3. Design and status of the NGNP fuel experiment AGR-3/4 irradiated in the advanced test reactor;Blaine Grover;Nucl. Eng. Des.,2014
4. Brown, N.R., Qualls, A.L., Betzler, B.R., Carbajo, J.J., Greenwood, M.S., Hale, R., Harrison, T.J., Powers, J.J., Robb, K.R., Core design characteristics of the fluoride salt-cooled high temperature demonstration reactor, ICAPP 2016: Nuclear Innovation: Inventing the Future of Existing and New Nuclear Power; April 17–20, San Francisco, CA, USA.
5. Carbajo, J.J. et al., 2010. Transient Thermal-Hydraulic Simulation of the Small Modular Advanced High-Temperature Reactor (SmAHTR), Trans. Am. Nucl. Soc. 103, Las Vegas, Nevada.
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