Subject
Nuclear Energy and Engineering
Reference40 articles.
1. Molten salt fast reactors;Allibert,2016
2. Calculating the effective delayed neutron fraction in the molten salt reactor: analytical, deterministic and Monte Carlo approches;Aufiero;Ann. Nucl. Energy.,2014
3. An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor;Aufiero;J. Nucl. Mater.,2013
4. The aircraft reactor experiment—design and construction;Bettis;Nucl. Sci. Eng.,1957
5. Briesmeister, J.F., 1997. MCNP4B – A general Monte Carlo N Particle Transport Code. LA-12625-M, Los Alamos Laboratory, Los Alamos, NM, USA.
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