Difference between revisions of "TF DOE EPSCOR 2018"
| Line 1: | Line 1: | ||
[[Forest_Proposals]] | [[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 | ||
| + | |||
| + | |||
| + | |||
[[File:NeutronFluxFromVariousFreactorTypes_BNL-4-23-2018.png | 400 px]] | [[File:NeutronFluxFromVariousFreactorTypes_BNL-4-23-2018.png | 400 px]] | ||
Revision as of 01:36, 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