A review of carbide fuel corrosion for nuclear thermal propulsion applications [electronic resource].

Published: Washington, D.C. : United States. Dept. of Energy, 1993.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description: 14 pages : digital, PDF file
Additional Creators: Los Alamos National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information

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Summary

At the operation conditions of interest in nuclear thermal propulsion reactors, carbide materials have been known to exhibit a number of life limiting phenomena. These include the formation of liquid, loss by vaporization, creep and corresponding gas flow restrictions, and local corrosion and fuel structure degradation due to excessive mechanical and/or thermal loading. In addition, the radiation environment in the reactor core can produce a substantial change in its local physical properties, which can produce high thermal stresses and corresponding stress fractures (cracking). Time-temperature history and cyclic operation of the nuclear reactor can also accelerate some of these processes. The University of New Mexico`s Institute for Space Nuclear Power Studies, under NASA sponsorship has recently initiated a study to model the complicated hydrogen corrosion process. In support of this effort, an extensive review of the open literature was performed, and a technical expert workshop was conducted. This paper summarizes the results of this review.

Report Numbers

E 1.99:la-ur--93-4136
E 1.99: conf-940101--26
conf-940101--26
la-ur--93-4136

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Note

Published through SciTech Connect.
12/01/1993.
"la-ur--93-4136"
" conf-940101--26"
"DE94003938"
": Grant NGT-40019"
"Grant NAG3-1346"
11. symposium on space nuclear power systems,Albuquerque, NM (United States),9-13 Jan 1994.
El-Genk, M.S.; Pelaccio, D.G.; Butt, D.P.

Funding Information

W-7405-ENG-36

View MARC record | catkey: 14458425