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- W1592988669 abstract "Clean criticality data were obtained from molybdenum-reflected cylindrical uranyl-fluoride-water solution reactors. Using ENDF/B molybdenum cross sections, a nine energy group two-dimensional transport calculation of a reflected reactor configuration predicted criticality to within 7 cents of the experimental value. For these reactors, it was necessary to compute the reflector resonance integral by a detailed transport calculation at the core-reflector interface volume in the energy region of the two dominant resonances of natural molybdenum." @default.
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- W1592988669 date "1972-07-01" @default.
- W1592988669 modified "2023-09-27" @default.
- W1592988669 title "Criticality experiments and analysis of molybdenum reflected cylindrical uranyl fluoride water solution reactors" @default.
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