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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
J. A. Vitti, P. K. Doherty, G. F. di Lauro, J. C. Gilbertson, D. W. Stuteville
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 442-451
Technical Paper | Fuel | doi.org/10.13182/NT75-A24444
Articles are hosted by Taylor and Francis Online.
A preliminary assessment of proof testing 13 prototypical liquid-metal fast breeder reactor (LMFBR) carbide fuel assemblies in fast test reactor (FTR) driver positions leads to the conclusion that the testing plan is practical and should produce a large amount of data at operating conditions very similar to those that would be found in large commercial carbide-fueled LMFBR s. Three subassembly configurations were designed, each capable of being directly substituted into FTR driver positions and made compatible with the FTR geometry, fuel handling, power, temperature, subassembly flow rates, and pin-bundle pressure drop. Two sodium-bonded designs, one with 91 fuel pins with a 0.370-in. o.d. and the other with 127 fuel pins with a 0.315-in. o.d. per subassembly were established. Calculated peak linear power and peak discharge burnup slightly exceed present commercial design objectives of 30 kW/ft and 73 MWd/kg. Individual assembly power history, flux, and enrichments are represented quite well in the FTR for commercial outer-zone fuel assemblies. Inner-zone operating conditions, however, are not simulated as closely. Impact effects of the proof-test assemblies on FTR operation are judged to be manageable.