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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Hot Fuel Examination Facility named a Nuclear Historic Landmark
The American Nuclear Society recently announced the designation of three new nuclear historic landmarks: the Hot Fuel Examination Facility (HFEF), the Neely Nuclear Research Center, and the Oak Ridge Gaseous Diffusion Plant. Today’s article, the first in a three-part series, will focus on the historical significance of HFEF.
Jeff A. Given, Samim Anghaie
Nuclear Technology | Volume 117 | Number 1 | January 1997 | Pages 87-108
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35338
Articles are hosted by Taylor and Francis Online.
A computational model for simulation and design analysis of nuclear thermal propulsion systems has been developed. The model simulates a full-topping expander cycle engine system and the thermofluid dynamics of the core coolant flow, accounting for the real gas properties of the hydrogen propellant/coolant throughout the system. Core thermofluid studies reveal that near-wall heat transfer models currently available may not be applicable to conditions encountered within some nuclear rocket cores. Additionally, the possibility of a core thermal fluid instability at low mass fluxes and the effects of the core power distribution are investigated. Results indicate that for tubular core coolant channels, thermal fluid instability is not an issue within the possible range of operating conditions in these systems. Findings also show the advantages of having a nonflat centrally peaking axial core power profile from a fluid dynamic standpoint. The effects of rocket operating conditions on system performance are also investigated. Results show that high temperature and low pressure operation is limited by core structural considerations, while low temperature and high pressure operation is limited by system performance constraints. The utility of these programs for finding these operational limits, optimum operating conditions, and thermal fluid effects is demonstrated.