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In quickest review, NRC approves 20-year renewal for Robinson
The Nuclear Regulatory Commission has renewed the Robinson nuclear power plant’s operating license in record time, the agency announced last week.
The subsequent license renewal process for the Hartsville, S.C., facility was completed within 12 months, according to the NRC. The process has typically taken 18 months. This was the first license renewal review conducted under the directive of Executive Order 14300 to streamline processes like renewing operating licenses.
Charles O. Slater, Hamilton T. Hunter
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 201-217
Technical Paper | Radiation Protection | doi.org/10.13182/NT00-A3057
Articles are hosted by Taylor and Francis Online.
Newly produced multigroup cross-section libraries require detailed testing to ensure that they are suitable for the applications intended. This requires that the libraries be tested against approved experimental benchmarks and/or well-posed calculational benchmarks. Following this tradition, the recently produced fine-group VITAMIN-B6 library and its derivative BUGLE-96 broad-group library have been tested against calculational and experimental benchmarks that are sensitive to neutrons with energies in the moderate-energy range (10.0 to 20.0 MeV). Iron is prominent in each benchmark as it is in many shielding configurations, and iron cross-section data have posed significant problems in many shielding designs. These benchmarks provide stringent tests for the iron cross sections. Calculated results obtained using the new libraries were compared to measured results or results from other calculations. In some cases, results were in good agreement. In other cases, there were significant discrepancies between results due to deficient measurements in a few comparisons and to method or data deficiencies in other comparisons. It is concluded that there is still need for further measurements and evaluations of the iron cross-section data in the energy region below 6.0 MeV. While fluxes in the moderate-energy range and the associated downscatter sources may be calculated adequately, the inadequate low-energy cross sections can lead to rather large discrepancies in integral quantities such as dose or heating.