Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
The purpose of this design analysis is to determine the accuracy of the SAS2H module of SCALE 4.3 in predicting isotopic concentrations of spent fuel assemblies. The objective is to develop a methodology for modeling assemblies similar to those evaluated within this analysis and to establish the consistency of SAS2H predictions. The results of this analysis may then be applied to future depletion calculations using SAS2H in which no measurements are available.
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
The purpose of this design analysis is to determine the accuracy of the SAS2H module of SCALE 4.3 in predicting isotopic concentrations of spent fuel assemblies. The objective is to develop a methodology for modeling assemblies similar to those evaluated within this analysis and to establish the consistency of SAS2H predictions. The results of this analysis may then be applied·to future depletion calculations using SAS2H in which no measurements are available. ·
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
This calculation compares results from criticality evaluations for a 21-assembly pressurized water reactor (PWR) waste package based on 12 axial burnup profile representations for commercial spent nuclear fuel (SNF) assemblies. The burnup profiles encompass the axial variations caused by different fuel assembly irradiation histories in a commercial PWR, including end effects, and the concomitant effect on reactivity in the waste package. The bounding axial burnup profiles in Table T of reference 6.3 are used for this analysis.
Presentation to the Nuclear Waste Technical Review Board (NWTRB) in regards to integrating standardization into the nuclear waste management system.
Nuclear Fuels Storage and Transportation Planning Project (NFST) Overview Presentation, 2014 Fuel Cycle Technologies (FCT) Annual Meeting, November 4-6, 2014, Idaho Falls, ID
Slides - Institute of Nuclear Materials Management, 55th Annual Meeting, July 20 – 24, 2014 Atlanta, Georgia
Slides - Institute of Nuclear Materials Management, 55th Annual Meeting, July 20 – 24, 2014 Atlanta, Georgia
Crystalline Repository Project Briefing
Presented to Blue Ribbon Commission on America's Nuclear Future
Site Evaluation and Management Lessons Learned from Yucca Mountain
