WCS Resolution
WCS Resolution
In the commissioners court of Andrews County, Texas
A resolution in support of establishing a site in Andrews County for consolidated interim storage of spent nuclear fuel and high-level radioactive waste.
In the commissioners court of Andrews County, Texas
A resolution in support of establishing a site in Andrews County for consolidated interim storage of spent nuclear fuel and high-level radioactive waste.
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.
<div class="page" title="Page 5">
<div class="layoutArea">
<div class="column">
<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>
Performance Specification: This performance specification document addresses use of a standardized transportation, aging, and
disposal (STAD) canister system in the spent nuclear fuel (SNF) waste management system. This
document was developed to support STAD canister system studies and potential research, development,
and demonstration activities. Requirements in this specification may evolve with time based on results
from analyses, experiments, design studies, system evaluations and demonstrations, as well as other
factors.
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.
This report provides information on the inventory of commercial spent nuclear fuel, referred to herein as used nuclear fuel (UNF), as well as Government-owned UNF and high-level radioactive waste (HLW). Actual or estimated quantitative values for current inventories are provided along with inventory forecasts derived from examining a different future commercial nuclear power generation scenarios. The report also includes select information on the characteristics associated with the wastes examined (e.g. type, packaging, heat generation rate, decay curves).
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.
On July 17, 2003, the U.S. Department of Energy (DOE) completed the movement of 125 commercial spent nuclear fuel (SNF) assemblies from the West Valley Demonstration Project (WVDP) to the Idaho National Engineering and Environmental Laboratory (INEEL). The assemblies were transported by rail in two dual-purpose shipping and storage casks specifically designed for the one shipment to the INEEL and for interim storage.
This report documents an initial evaluation of integrating standardized canisters into the nuclear waste management system, which is an intermediate step in the quantitative assessment of standardization. This is a technical report that does not take into account the contractual limitations under the Standard Contract (10 CFR Part 961) that DOE has in place with nuclear utilities. Under the Standard Contract, DOE is obligated to accept only bare UNF. Acceptance of canistered UNF would require a mutual agreement to modify the contract.
Safety Analysis report for the NAC International, Legal Weight Truck spent fuel shipping cask (NAC-LWT.) Shipment of the NAC-LWT cask can be made by truck, ISO container, and/or by railcar, as a Type B(U)F-96 package, as defined in 10 CFR 71.4. The NAC-LWT cask is a stainless steel and lead shielded cask with a surrounding water-ethylene glycol neutron
shield. The cask, which has capacity to ship 1 PWR or 2 BWR used nuclear fuel assemblies, is designed to be transported using legal-weight trucks having a fully loaded gross vehicle weight that does not exceed 80,000 lbs.
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).
This issue brief is one in a series being developed by the Bipartisan
Policy Center’s Nuclear Waste Initiative, which is exploring ways
to advance progress toward durable solutions for managing and
disposing of the nation’s inventory of spent nuclear fuel and highlevel
radioactive waste. This brief focuses on options for moving
forward with the development of one or more facilities for the
consolidated storage of spent fuel from commercial nuclear power
plants. It is based on a longer analysis prepared for the Bipartisan