Difference between revisions of "TF DOE EPSCOR 2018"
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FHR: Nicholas R. Brown et al., "Preconceptual Design of a Fluoride High Temperature Salt-Cooled Engineering Demonstration Reactor: Core Design and Safety Analysis." Annals of Nuclear Energy 103, pp 49-59, 2017. | FHR: Nicholas R. Brown et al., "Preconceptual Design of a Fluoride High Temperature Salt-Cooled Engineering Demonstration Reactor: Core Design and Safety Analysis." Annals of Nuclear Energy 103, pp 49-59, 2017. | ||
Revision as of 01:37, 10 December 2018
Neutron flux from various reactor types
FHR: Nicholas R. Brown et al., "Preconceptual Design of a Fluoride High Temperature Salt-Cooled Engineering Demonstration Reactor: Core Design and Safety Analysis." Annals of Nuclear Energy 103, pp 49-59, 2017.
MCFR: M. Taube and J. Ligou. "Molten Plutonium Chlorides Fast Breeder Reactor Cooled by Molten Uranium Chloride," Annals of Nuclear Science and Engineering, 1.4, pp 277-281, 1974
IS_MSR: N.R.Brown et al., “Sustainable Thorium Nuclear Fuel Cycles: A Comparison of Intermediate and Fast Neutron Spectrum Systems,” Nuclear Engineering and Design, 289, pp 252-265, 2015.
LWR: generic light water reactor SFR: Sodium cooled fast reactor
BNL report from 4/23/18 on Phenomena Important in Modeling and Simulation of Molten Salt Reactors
Media:BNL_Report_4_23_2018.pdf