An Extension of the Validation of SCALE (SAS2H) Isotopic Predictions for PWR Spent Fuel

Abstract

IThis report has been reproduced directly from the best available copy.Availabte to DOE and DOE contractors from the Office of Scientific and Technical Information, P.0.Box 62, Oak Ridge, TN 37831; prices available from (423) 576-8401, FTS 626-8401Available to the public from the National Technical Information Service, U.S. Department of Commerce, 5285 Port Royal Rd., Springfield, VA 22161 I This report was prepared a an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The view and opinions of authors expressed herein do not necessarily state or reflect those of the UnitedStatesGovemment or any agency thereof. DISCLAIMERPortions of this document may be illegible in electronic image products. Images are produced from the best available original document. In addition, an approach to determine biases and uncertainties between calculated and measured isotopic concentrations is discussed, together with a method to statistically combine these terms to obtain a conservative estimate of spent fuel isotopic concentrations. Results are presented based on the combination of measured-to-calculated ratios for earlier work and the current analyses.The results described herein represent an extension to a new reactor design not included in the earlier work, and spent fuel samples with enrichment as high as 3.9 wt % u5U. Results for the current work are found to be, for the most part, consistent with the findings of the earlier work. This consistency was observed for results obtained from each of two different crosssection libraries and suggests that the estimated biases determined for each of the isotopes in the earlier work are reasonably good estimates, as the additional measurement/calculated ratios resulting from the current work tend to confirm these estimates. vii ACKNOWLEDGMENTS

Nuclear georeactor origin of oceanic basalt 3 He/ 4 He, evidence, and implications

“…Calculations were made with the SAS2 analysis sequence contained in the SCALE Code Package from the Oak Ridge National Laboratory (18) that has been developed over 30 years and has been extensively validated against isotopic analyses of commercial reactor fuels (19)(20)(21)(22)(23). The SAS2 sequence invokes Abbreviations: RA, ratio relative to air; TW, Terra-watt.…”

Development of Neutron Energy Spectral Signatures for Passive Monitoring of Spent Nuclear Fuels in Dry Cask Storage

“…The ORIGEN-S code and associated nuclear data libraries have been through numerous verification and validation benchmarks. These included validation against more than 100 spent fuel samples from domestic and international programs involving older and modern high-burnup mixed oxide (MOX) and low-enriched uranium (LEU) fuels [8].…”

Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel

“…As indicated earlier, validation of calculated isotopic predictions against experimental measurements is desirable for any nuclide upon which burnup credit criticality calculations are based. Isotopic validation studies using the SCALE/SAS2H depletion sequence and available measured assays have been performed for PWR spent fuel 24,25 and BWR spent fuel. 26 For BWR fuel, the number of nuclides for which there are measured data is significantly reduced and is limited primarily to the actinides of Table 2.…”