Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
The objective of this analysis is to characterize a codisposal canister containing MIT or ORR fuel in the Five-Pack Defense High-Level Waste (5-DHLW) Waste Package (WP) to demonstrate concept viability related to use in the Mined Geologic Disposal System (MGDS) environment for the postclosure time frame. The purpose of this analysis is to investigate the disposal criticality and shielding issues for the DHLW WP and establish DHLW WP and codisposal canister compatibility with the MGDS, and to provide criticality and shielding evaluations for the preliminary DHLW WP design.
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. The analytical model employed for this analysis was the SAS2H module of the SCALE sequence.
Presentation to the Nuclear Waste Technical Review Board (NWTRB) in regards to integrating standardization into the nuclear waste management system.
The purpose of this calculation is to perform an example criticality evaluation for degraded internal configurations of a boiling water reactor (BWR) waste package (WP) containing 44 spent nuclear fuel (SNF) assemblies. The BWR assembly design considered is based on the General Electric (GE) 8x8 assembly (see section 5.1). Depletion analyses for various assembly average enrichment and burnup (expressed as gigawatt days/metric ton Uranium; GWd/MTU) combinations are performed using the SAS2H/ORIGEN-S sequence of SCALE 4.3 (CSCI:30011-2002; Ref. 7.5).
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
