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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.
Ross C. Anderson
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 247-250
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34560
Articles are hosted by Taylor and Francis Online.
Improvements in thermal margin analyses have, in recent years, been dominated by the use of statistical methods to combine the correlation uncertainty with other key uncertainties such as those in temperature, power, or the radial power factor. The methods of combination have included both root-sum-square and Monte Carlo. The latter method provides insight into the probability density function of the composite departure from nucleate boiling ratio, which, for a measured-to-predicted-normal correlation uncertainty and commonly used parameter uncertainties, proves to be skewed slightly upward from normal. In such a case, the assumption of normality is a conservative assumption in licensing analyses.