Alternative Cask and Canister Concepts for Storage, Transportation, and/or Emplacement
Alternative Cask and Canister Concepts for Storage, Transportation, and/or Emplacement
Presentation to NWTRB by OCRWM representative.
Presentation to NWTRB by OCRWM representative.
Virginia Power presentation to NWTRB on universal container concepts.
Presentation to Nuclear Waste Technical Review Board. Summarizes work performed for the EPRI report TR-101988 published in 1993 by EPRI. This examines a universal canister concept as well as a universal cask concept, and performs a systems analysis. Prepared by E.R. Johnson Associates Inc.
This paper describes the lessons learned from the U.S. Department of Energy (DOE) transportation of
125 DOE-owned commercial spent nuclear fuel (SNF) assemblies by railroad from the West Valley Demonstration
Project to the Idaho National Engineering and Environmental Laboratory (INEEL). On July 17, 2003, DOE made
the largest single shipment of commercial SNF in the history of the United States. This was a highly visible and
political shipment that used two specially designed Type B transportation and storage casks. This paper describes
A comprehensive, integrated data and analysis tool—the Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS) —is being developed for the US DOE Office of Nuclear Energy (DOE-NE) Nuclear Fuels Storage and Transportation Planning Project (NFST). The overarching goal of UNF-ST&DARDS is to provide a comprehensive controlled source of technical data integrated with key analysis capabilities to characterize inputs to the overall US waste management system from reactor power production through ultimate disposition.
This presentation was presented at the WM2015 presentation in Phoenix, AZ on March 17, 2015.
This presentation was given at WM2015 in Phoenix, AZ on March 18, 2015.
This paper assesses the feasibility of direct disposal of loaded dual-purpose canisters (DPCs) from a criticality standpoint by evaluating attributes that could be credited to justify that the DPCs remain subcritical over a repository performance period. This study investigates the uncredited criticality margin associated with actual fuel loading compared with the regulatory licensing design basis limits and evaluates the percentage of DPCs that remain subcritical solely based on the uncredited criticality margin.
Social Scientists such as Hank Jenkins-Smith from the University of Oklahoma have suggested that the structured evaluation of beliefs and preferences measured in annual survey and social media data streams can assist program managers in making nuclear facility siting programs responsive and adaptive to the evolution of nuclear narratives. This presentation will provide an engineering and project management perspective on how ongoing social science research can be used.
Slides - Institute of Nuclear Materials Management, 55th Annual Meeting, July 20 – 24, 2014 Atlanta, Georgia
Slides - Institiute of Nuclear Materials Management Annual Meeting (INMM), Atlanta GA, July 20-24, 2014
Slides - Institute of Nuclear Materials Management Annual Meeting, Atlanta GA, July 20-24, 2014
Slides - Institute of Nuclear Materials Management Annual Meeting (INMM), July 20-24 2014, Atlanta GA
Slides - Institute of Nuclear Materials Management, 55th Annual Meeting, July 20 – 24, 2014 Atlanta, Georgia
<p>This presentation was given at Oak Ridge National Laboratory on May 20, 2014. It describes the Centralized Used Fuel Resource for Information Exchange (CURIE) and how to register, log-in, and upload documents among other capabilities. </p>
Slides - 2014 National Tranpsortation Stakeholders Forum, Bloomington, MN, May 13-15, 2104
Understanding the changing nuclear and mechanical characteristics of used nuclear fuel (UNF) over time and how these changing characteristics affect storage, transportation, and disposal options can require many tools and types of data. To streamline analysis capabilities for the waste management system, a comprehensive, integrated data and analysis tool has been assembled—UNF-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS).
Presentation by Ron Pope and Yung Liu of Argonne National Laboratory to the World Institute for Nuclear Security (WINS) Workshop on Security of Dry Storage of Spent Nuclear Fuel
Slides - World Institute for Nuclear Security (WINS), Security of Dry Storage of Spent Nuclear Fuel, Vilnius, Lithuania, June 10-12, 2014
Slides - National Tranpsortation Stakeholders Forum, Minneapolis, MN, May, 14, 2014
Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.
This presentation was given at the Nuclear Waste Technical Review Board (NWTRB) meeting June 24, 2015 in Golden, Colorado. It covered the standardized transportation, aging, and disposal (STAD) canister design work being performed by DOE and responded to a number of NWTRB questions.
These slides were presented by Waste Control Specialists LLC (WCS) to the NRC at the June 16, 2015 pre-application public meeting at the NRC offices in Rockville, Maryland.