Transportation System Concept of Operations
Transportation System Concept of Operations
DOE/RW-0584
DOE/RW-0584
This report was prepared for the Secretary of Energy by a team of federal and contractor
personnel led by the Department’s Office of Nuclear Energy. The report assesses the technical
options for the permanent disposal of high-level radioactive waste (HLW) and spent nuclear fuel
(SNF) managed by the Department of Energy. Specifically, it considers whether DOE-managed HLW and
SNF should be disposed of with commercial SNF and HLW in one geologic repository or whether there
This three-volume report serves several purposes. The first volume provides an
introduction to the engineered materials effort for the Yucca Mountain Site
Characterization Project. It defines terms and outlines the history of selection and
characterization of these materials. A summary of the recent engineered barrier
system materials characterization workshop is presented, and the current candidate
materials are listed.
Presentation to the Nuclear Waste Technical Review Board regarding the Westinghouse MPC design.
This report describes a task performed in the Energy Material Transport,
Now Through 2000, System Characteristics and Potential Problems (Transportation
Problems) Project. This project was sponsored by the Department of Energy,
Environmental Control Technology Division. The DOE Project Monitor was
R. F. Garrison; Project Manager at PNL was J. G. DeSteese. A continuation of
the cask turnaround study is currently supported by the Transportation Technology
Center at Sandia National Laboratories, the DOE1s lead laboratory for Transportation
Presentation to NWTRB by OCRWM representative.
Virginia Power presentation to NWTRB on universal container concepts.
A Program Research and Development Announcement (PRDA) was
initiated by DOE to solicit from industry new and novel ideas for
improvements in the nuclear waste management system. GA Technologies
Inc. was contracted to study a system utilizing a universal canister
which could be loaded at the reactor and used throughout the waste
management system.
Lists Various TVA Activities Involving Spent Fuel
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.
The objective of this siting study work is to support DOE in evaluating integrated advanced nuclear plant and ISFSI deployment options in the future. This study looks at several nuclear power plant growth scenarios that consider the locations of existing and planned commercial nuclear power plants integrated with the establishment of consolidated interim spent fuel storage installations (ISFSIs).
HR1146 Report - Response to the Illinois General Assembly concerning House Resolution 1146.
This report is part of study to identify reference geologic disposal concepts for generic studies in the Used Fuel Disposition R&D Campaign. This report summarizes the work on both enclosed and open modes, which has been expanded to include thermal analysis of open modes, a range of spent nuclear fuel (SNF) burnup, additional disposal system description, and cost estimation.
The Standard Review Plan for Transportation Packages for Spent Nuclear Fuel provides NRC guidance for the review and approval of applications for packages used to transport spent nuclear fuel under 10 CFR Part 71.
The purpose of this study is to analyze the costs and risks associated with transporting spent fuel by barge. The barge movements would be made in combination with rail movements to transport spent fuel from plants to a repository. For the purposes of this analysis, three candidate repository sites are analyzed: Yucca Mountain, Nevada, Deaf Smith, Texas, and Hanford, Washington. This report complements a report prepared by Sandia National Laboratories in 1984 that analyzes the costs and risks of transporting spent
fuel by rail and by truck to nine candidate repository sites.
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 report (PNL-6906 Vol. 1) documents activation measurements and comparison with calculations for spent fuel assembly hardware.
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