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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.
Grover Tuck
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 177-188
Chemical Processing | Nuclear Safeguards (Presented at November 1973 Meeting) | doi.org/10.13182/NT23-177
Articles are hosted by Taylor and Francis Online.
Simplified methods of estimating the results of accidental solution excursions in tanks have been developed. With these methods, an estimate of the number of fissions in the burst, total fissions, or maximum power level can usually be obtained with a desk calculator. The equation parameters are tank diameter, height, and fill rate. The fissile material concentration is not required since, in each case, the “worst-case” concentration was assumed in the derivation of the equation. These methods are sufficiently accurate for most calculations required for safety analysis reports and process plant design. The severity of an excursion can be limited by several methods which include criticality alarm activated shut-off valves in the feed lines, remote tank drain capability, minimizing tank size, etc.