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Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
M. Makai, E. Temesvári
Nuclear Science and Engineering | Volume 112 | Number 1 | September 1992 | Pages 66-77
Technical Paper | doi.org/10.13182/NSE92-A23952
Articles are hosted by Taylor and Francis Online.
Surveillance of a nuclear reactor core involves determination of the power or temperature distribution of the assemblies. Derived from other assemblies’ measured temperatures, the temperature of a nonmeasured assembly is calculated for every assembly with the help of the principal components method (PCM). The basis of this method is presented, and the measured values are interpolated for various geometrical coverings of the WWER-440 core. A number of procedures have been elaborated and investigated, the most successful of which are introduced. Each method offers self-consistent means for determining the numerical errors of the interpolated values. The procedure based on the PCM can be utilized for any reactor type and is fairly accurate.