Design and Analysis of a 250 MW Plate-fuel Reactor for Nuclear Thermal Propulsion

Conference · Thu Apr 30 04:00:00 EDT 2020

OSTI ID:1638498

Lin, Ching-Sheng ^[1]; Youinou, Gilles J ^[1]

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1. Idaho National Laboratory

Nuclear thermal propulsion (NTP) system is a viable option for deep space missions considering its high thrust and lightweight. Promising fuel options being considered for the high operating temperature of NTP include the graphite composite fuel and the tungsten cermet fuel. As there remains uncertainties in the fabrication and performance of these two fuel elements, alternative designs using fuel plates and more standard fuels that are based on proven and tested nuclear technologies are being considered. This paper provides a summary of thermal hydraulic and neutronic analyses of the straight fuel plate concept used for a 250 MW NTP core. The summary of technical findings from a series of scoping studies might be useful for the future NTP engine designs.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: DOE’s NTP project; USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1638498
• Report Number(s): INL/CON-19-56926-Rev000
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
nuclear thermal propulsion