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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.
Antonio F. Dias, Laurance D. Eisenhart, Ronald E. Engel, Lance J. Agee
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 346-358
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2846
Articles are hosted by Taylor and Francis Online.
The rod ejection accident in a pressurized water reactor and the control rod drop accident in a boiling water reactor are analyzed in this paper, both in a best-estimate (realistic) and a conservative manner. CORETRAN, a modern three-dimensional time-dependent nodal code, is used for all simulations. In all considered cases, the resulting peak fuel enthalpy is far less than the current licensing limit of 180 cal/g. The advantage of using a three-dimensional code over the classical point-kinetics approach can be summarized: The power peak is nominally a factor of 10 times lower, and the pulse is 10 times wider. Therefore, a three-dimensional approach predicts a much milder event. Sensitivity studies were performed to identify the influence of several parameters on the reactivity insertion simulations.