Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis

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

Publisher

Elsevier BV

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.

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