TF DOE EPSCOR 2018

From New IAC Wiki
Revision as of 01:37, 10 December 2018 by Foretony (talk | contribs)
Jump to navigation Jump to search

Forest_Proposals

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



NeutronFluxFromVariousFreactorTypes BNL-4-23-2018.png

BNL report from 4/23/18 on Phenomena Important in Modeling and Simulation of Molten Salt Reactors

Media:BNL_Report_4_23_2018.pdf


Forest_Proposals