<p>MULTI-PURPOSE CANISTER PROCUREMENT: A SIGNIFICANT STEP FOR THE DEPARTMENT OF ENERGY'S CIVILIAN RADIOACTIVE WASTE MANAGEMENT PROGRAM</p>
<p>A newsletter from the Office of Civilian Radioactive Waste Management</p>
<p>Highlights include...</p>
<p>Westinghouse begins designing multi-purpose canister</p>
<p>DOE accepts General Atomics-9 assembly transportation cask trailer</p>
<p>Final interpretation of nuclear waste acceptance issues published</p>
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).
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.
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 - Institute of Nuclear Materials Management, 55th Annual Meeting, July 20 – 24, 2014 Atlanta, Georgia
This document is a compilation of publically-available information on spent/used nuclear fuel storage and transport casks in use in the United States as of the summer of 2013. As such, it is a functional update and extension of JAI-582, “Shipping and Storage Cask Data For Commercial Spent Nuclear Fuel,” originally published by JAI Corporation in March 2005[1]. This report is intended to provide a convenient reference for those with interest in, or those engaged in the production, handling, storage, transport, and disposition of spent/used commercial nuclear fuel.
The Yucca Mountain repository is designed to provide a permanent solution for managing nuclear waste, minimize the uncertainty of future waste safety, and enable DOE to begin fulfilling its legal obligation under the Nuclear Waste Policy Act to take custody of commercial waste, which began in 1998. However, project delays have led to utility lawsuits that DOE estimates are costing taxpayers about $12.3 billion in damages through 2020 and could cost $500 million per year after 2020, though the outcome of pending litigation may affect the government’s total liability.
<p>Regulatory Guide 1.60 DESIGN RESPONSE SPECTRA FOR SEISMIC DESIGN OF NUCLEAR POWER PLANTS</p>
This publication is a compilation of international experience with cask contamination problems
and decontamination practices. The objective is to represent current knowledge and experience as well
as developments, trends and potential for new applications in this field. Furthermore, the report may
assist in new design or modification of existing casks, cask handling systems and decontamination
equipment. The annexes contain figures of several cask types for illustration.
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<p><span style="font-size: 12.000000pt; font-family: 'TimesNewRomanPSMT'">This report fulfills the M1 milestone M11UF041401, “Storage R&D Opportunities Report” under Work Package Number FTPN11UF0414. </span></p>
<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>
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
The main question before the Transportation and Storage Subcommittee was whether the United States should change its approach to storing and transporting spent nuclear fuel (SNF) and high-level radioactive waste (HLW) while one or more disposal facilities are established.
The criticality consequence analysis for pressurized water reactor (PWR) waste packages (WP)
(Civilian Radioactive Waste Management System [CRWMS] Management and Operating
Contractor [M&O] 1997) focused on results obtained by maximizing postulated rates of
reactivity insertion to assure no synergistic reactions could occur among waste packages from
hypothetical criticality events. Other variables potentially influencing the criticality
consequences were held constant during the above referenced analysis. One of those variables
The American Nuclear Society (ANS) appreciates the opportunity to comment on the draft Nuclear Waste Administration Act (NWAA). The ANS is a not-for-profit, international, scientific, and educational organization with nearly 12,000 members worldwide. The core purpose of ANS is to promote awareness and understanding of the application of nuclear science and technology. As an organization, it has published a number of position statements regarding the issue of spent fuel and radioactive waste.
The purpose of this calculation is to characterize the criticality aspect of the codisposal of TRIGA (Training, Research, Isotopes, General Atomic) reactor spent nuclear fuel (SNF) with Savannah River Site (SRS) high-level waste (HLW). The TRIGA SNF is loaded into a Department of Energy (DOE) standardized SNF canister which is centrally positioned inside five-canister defense SRS HLW waste package (WP). The objective of the calculation is to investigate the criticality issues for the WP containing the five SRS HLW and DOE SNF canisters in various stages of degradation.
