Integrated Cask Storage Systems for Storage, Transportation, and Disposal of Spent Nuclear Fuel
Integrated Cask Storage Systems for Storage, Transportation, and Disposal of Spent Nuclear Fuel
Lists Various TVA Activities Involving Spent Fuel
Lists Various TVA Activities Involving Spent Fuel
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.
This report (PNL-6906 Vol. 1) documents activation measurements and comparison with calculations for spent fuel assembly hardware.
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>
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.
This CSNF handling study evaluates the handling of CSNF in air and packaging activities. It evaluates a facility design, further identifies the fuel performance issues, develops the consequences, and presents the operational considerations associated with the routine handling of CSNF in air. Emphasis is on the process of oxidation of
uranium dioxide fuel and additional oxidation-driven failure of fuel assembly cladding. Key
issues are identified, and plans to address these issues are proposed.
Per the requirements of the Task Order 21: Operational Requirements for Standardized Dry Fuel Canister Systems, Statement of Work (SOW), EnergySolutions and its team partners: NAC International, Booz Allen Hamilton and Exelon Nuclear Partners, hereafter referred to as “the Team”, is providing for the U.S. Department of Energy (DOE) an Updated Final Report, which documents the results from the studies performed.
Under Task Order 17 of the industry Advisory and Assistance Contract to the Department of
Energy (DOE) DE-NE0000291, the AREVA Team has provided a conceptual design for a
reusable transportation cask (the 6625B-HB) capable of transporting BWR and PWR used
nuclear fuel (UNF) assemblies, including high burnup UNF. These assemblies can be shipped
either as bare fuel or fuel loaded into damaged fuel canisters (DFCs). The 6625B-HB cask has
been designed with reasonable assurance it can be licensed by the Nuclear Regulatory
This report documents the concepts, feasibility, advantages, disadvantages and recommendations for STAD canister systems developed by EnergySolutions and its team of partners: NAC International, Talisman International, Booz Allen Hamilton, TerranearPMC, Exelon Nuclear Partners and Sargent & Lundy, hereafter referred to as “the Team”.
Per the requirements of the Task Order 17: Spent Nuclear Fuel Transportation Cask Design
Study, statement of work (SOW), EnergySolutions and its team partners: NAC International,
Talisman International, Booz Allen Hamilton and Exelon Nuclear Partners, hereafter referred to
as “the Team”, is providing a final report for U.S. Department of Energy (DOE) review, which
documents the cask concepts developed under this study and the results of supporting analysis
work.
The “Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste” report was issued by the Department of Energy (DOE) in January 2013. The strategy includes a phased, adaptive, and consent based approach to siting and implementing a comprehensive management and disposal system. It also endorses a waste management system containing a pilot interim storage facility and a full-scale interim storage facility, which prioritizes the acceptance of fuel from shut-down reactors. Required features of the system and facilities are:
1.0 INTRODUCTION
Under a contract with the Department of Energy (DOE), the AREVA Team has evaluated the alternatives for developing a used nuclear fuel (UNF) Consolidated Storage Facility (CSF) for UNF from US reactor plants. The study, based upon specific criteria and requirements for the US, considered numerous credible storage options and selected the one that met the needs of the country. For this task, the AREVA Team comprises AREVA, URS, Duke Energy, Dominion, and Coghill Communications, Inc.
1.1 Purpose
This report has been prepared by the industry team of Shaw Environmental & Infrastructure,
Inc. (Shaw) and Longenecker & Associates (L&A) in response to the Department of Energy
(DOE) Statement of Work, “Development of Consolidated Storage Facility Design
Concepts,” indefinite delivery/indefinite quantity Task Order No. 11, as specified by the
DOE’s Office of Nuclear Energy.
The Department of Energy (DOE) issued its Strategy for the Management and Disposition of Used
Nuclear Fuel and High-Level Radioactive Waste in January 2013. DOE undertook studies and analyses
to determine systems and design concepts as a preliminary step to further defining systems, equipment,
and facilities to implement the Strategy. This report uses the work performed by industry and national
laboratories and configures system components to meet the requirements of the Strategy. The project
In the 1990s the U.S. Department of Energy (DOE) completed a number of system analyses investigating consolidated interim storage as a part of the waste management solution. These analyses are “dated” and do not reflect the present situation regarding at-reactor used nuclear fuel (UNF) management, alternatives for away from reactor management of used nuclear fuel, and alternatives for the ultimate disposal of UNF.
The report, Commercial Spent Nuclear Fuel and High-Level Radioactive Waste Inventory Report(FCRD-NFST-2013-000263, Rev.3), provides information on the inventory of commercial spent fuel, referred to in this report as used nuclear fuel (UNF), as well as Government-owned UNF and High Level Waste (HLW) in the U.S. Department of Energy (DOE) complex. Inventory forecasts for commercial UNF were made for a few selected scenarios of future commercial nuclear power generation involving the existing reactor fleet including one scenario involving reactors under construction.
The Centralized Interim Storage Facility (CISF) is designed as a temporary, above-ground away-from-reactor spent fuel storage installation for up to 40,000 metric tons of uranium (MTU). The design is non-site-specific but incorporates conservative environmental and design factors (e.g., 360 mph tornado and 0.75 g seismic loading) intended to be capable of bounding subsequent site-specific factors. Spent fuel is received in dual-purpose canister systems and/or casks already approved for transportation and storage by the Nuclear Regulatory Commission (NRC).
In the course of producing electrical power in light water reactors (LWRs), the uranium
fuel accumulates fission products until the fission process is no longer efficient.for power
production. At that point the fuel is removed from the reactor and stored in water basins
to allow radioactivity to partially decay before further disposition. This fuel is referred
to as "spent fuel." Although spent fuel as it is discharged from a reactor is intensely
radioactive, it has been stored safely in moderate quantities for decades. Spent fuel could
Analytical methods, described in this report, are used to
systematically determine experimental fuel sub-batch
reactivities as a function of burnup. Fuel sub-batch reactivities
are inferred using more than 600 in-core pressurized water
reactor (PWR) flux maps taken during 44 cycles of operation
at the Catawba and McGuire nuclear power plants. The
analytical methods systematically search for fuel sub-batch
reactivities that minimize differences between measured and
computed reaction rates, using Studsvik Scandpower’s