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Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada (40 CFR Part 197) -- Final Rule Response to Comments Document
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada (40 CFR Part 197) -- Final Rule Response to Comments Document
EPA held a 90-day public comment period for the proposed radiation protection standards for Yucca Mountain (August 27, 1999 through November 26, 1999). Sixty-nine (69) sets of written comments were submitted to EPAÕs Air Docket regarding the proposed standards, although some commenters submitted more than one set of written comments. In addition, the Agency received oral testimony on the proposed standards from 28 speakers during public hearings that were held in Washington, DC; Las Vegas, NV; Amargosa Valley, NV; and Kansas City, MO.
Gap Analysis to Support Extended Storage of Used Nuclear Fuel
Gap Analysis to Support Extended Storage of Used Nuclear Fuel
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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>
Summary Statement - Regulations for Geological Disposal of High-Level Radioactive Waste
Summary Statement - Regulations for Geological Disposal of High-Level Radioactive Waste
Presented on September 2010 to the Blue Ribbon Commission on America's Nuclear Future (Disposal Subcommittee)
NFST Transportation Program Overview
NFST Transportation Program Overview
Slides - 2014 National Tranpsortation Stakeholders Forum, Bloomington, MN, May 13-15, 2104
UNF-STANDARDS presentation to EPRI extended storage collaboration project
UNF-STANDARDS presentation to EPRI extended storage collaboration project
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).
Transport Security - Security of Spent Nuclear Fuel in Transport and Dry Storage
Transport Security - Security of Spent Nuclear Fuel in Transport and Dry Storage
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
What to Expect When Readying to Move Spent Nuclear Fuel from Commercial Nuclear Power Plants
What to Expect When Readying to Move Spent Nuclear Fuel from Commercial Nuclear Power Plants
Slides - National Tranpsortation Stakeholders Forum, Minneapolis, MN, May, 14, 2014
Geological Disposal of Higher Activity Radioactive Wastes
Geological Disposal of Higher Activity Radioactive Wastes
This is one of three CoRWM reports to Government in 2009. The reports are about: <br><br>_ interim storage of higher activity wastes (including waste conditioning, packaging and transport, and the management of materials that may be declared to be wastes) <br>_ the implementation of geological disposal of higher activity wastes (this report) <br>_ research and development for interim storage and geological disposal. <br><br>The reports cover the three strands of the Government_s Managing Radioactive Waste Safely programme.
EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume IV—Lessons Learned
EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume IV—Lessons Learned
The effective termination of the Yucca Mountain program by the U.S. Administration in 2009
has further delayed the construction and operation of a permanent disposal facility for used fuel
and high level radioactive waste (HLW) in the United States. In concert with this decision, the
President directed the Energy Secretary to establish the Blue Ribbon Commission on America’s
Nuclear Future to review and provide recommendations on options for managing used fuel and
Assessment of Accident Risk for Transport of Spent Nuclear Fuel to Yucca Mountain Using RADTRAN 5.5
Assessment of Accident Risk for Transport of Spent Nuclear Fuel to Yucca Mountain Using RADTRAN 5.5
This report evaluates the radiological impacts during postulated accidents associated with the
transportation of spent nuclear fuel to the proposed Yucca Mountain repository, using the
RADTRAN 5.5 computer code developed by Sandia National Laboratories. RADTRAN 5.5 can
be applied to estimate the risks associated both with incident-free transportation of radioactive
materials as well as with accidents that may be assumed to occur during transportation. Incidentfree
transportation risks for transport of spent nuclear fuel to Yucca Mountain were evaluated in
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada; Final Rule
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada; Final Rule
We, the Environmental Protection Agency (EPA), are promulgating public health and safety standards for radioactive material stored or disposed of in the potential repository at Yucca Mountain, Nevada. Section 801 of the Energy Policy Act of 1992 (EnPA, Pub. L. 102Ð486) directs us to develop these standards. Section 801 of the EnPA also requires us to contract with the National Academy of Sciences (NAS) to conduct a study to provide findings and recommendations on reasonable standards for protection of the public health and safety.
Transportation and Storage Subcommittee Report to the Full Commission Updated Report
Transportation and Storage Subcommittee Report to the Full Commission Updated Report
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.
Critical Comments on the US EPA Standard 40 CFR 191
Critical Comments on the US EPA Standard 40 CFR 191
This paper is about the U.S. Environmental Protection Agency (EPA) "Environmental Standards for the Disposal of Spent Nuclear Fuel, High-Level and Transuranic Wastes, " 40 CFR 191. These standards regulate the disposal of radioactive wastes in geologic repositories.
West Valley Spent Fuel Shipment Project - Lessons Learned
West Valley Spent Fuel Shipment Project - Lessons Learned
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.
ANDRA The french national radioactive waste management agency
ANDRA The french national radioactive waste management agency
Waste management operation began in France in 1969. Created in 1979 as an agency within the CEA, ANDRA was established by the December 1991 Waste Act as an independent public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministries in charge of Energy, Ecology, and Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act (www.andra.fr).
A review of the Nuclear Waste Disposal Problem
A review of the Nuclear Waste Disposal Problem
Dealing with the problems posed by nuclear waste management is a major issue confronting continued use of the nuclear fuel cycle. Large amounts of radioactive wastes have already been generated as a result of past nuclear reactor operations, but these wastes are being temporarily kept in aboveground storage facilities awaiting a government policy decision on final disposition. Although research on various technologies to dispose of radioactive wastes is given high priority, a commercial waste disposal facility is not expected to be in operation before 1985.
POSITION PAPER ON PUBLIC AND STAKEHOLDER ENGAGEMENT
POSITION PAPER ON PUBLIC AND STAKEHOLDER ENGAGEMENT
This document does not present the views of the Committee on Radioactive Waste Management nor can it be taken to present the views of its author. It is a draft paper to inform Committee deliberations and both the author and the whole Committee may adopt different views and draw entirely different conclusions after further consideration and debate
POSITION PAPER ON PUBLIC AND STAKEHOLDER ENGAGEMENT for Discussion and Decision
POSITION PAPER ON PUBLIC AND STAKEHOLDER ENGAGEMENT for Discussion and Decision
This document does not present the views of the Committee on Radioactive Waste Management nor can it be taken to present the views of its author. It is a draft paper to inform Committee deliberations and both the author and the whole Committee may adopt different views and draw entirely different conclusions after further consideration and debate
Destructive Examination of 3-Cycle LWR Fuel Rods from Turkey Point Unit 3 for the CLIMAX-Spent Fuel Test
Destructive Examination of 3-Cycle LWR Fuel Rods from Turkey Point Unit 3 for the CLIMAX-Spent Fuel Test
The destructive examination results of five light water reactor rods from the Turkey Point Unit 3 reactor are presented. The examinations included fission gas collection and analyses, burnup and hydrogen analyses, and a metallographic evaluation of the fuel, cladding, oxide, and hydrides. The rods exhibited a low fission gas release with all other results appearing representative for pressurized water reactor fuel rods with similar burnups (28 GWd/MTU) and operating histories.
Characterization of LWR Spent Fuel MCC-Approved Testing Material - ATM-101
Characterization of LWR Spent Fuel MCC-Approved Testing Material - ATM-101
This report describes the characterization plan, methods, and results for light water reactor (LWR) Materials Characterization Center (MCC) spent fuel Approved Testing Material (ATM)-101. ATM-101 is spent fuel from H. B. Robinson, Unit 2, Assembly B0-5, a moderate-burnup, pressurized water reactor (PWR) fuel that released very small quantities of fission products and fission gas from the fuel during commercial operation.
SITING PROCESS FOR HLW REPOSITORY IN JAPAN
SITING PROCESS FOR HLW REPOSITORY IN JAPAN
In the year 2000, the geological disposal program for high-level radioactive waste in Japan moved from the phase of generic research and development (R&D) into the phase of implementation. Following legislation entitled the “Specified Radioactive Waste Final Disposal Act”, the Nuclear Waste Management Organization of Japan (NUMO) was established as the implementing organization.
[AREVA] Task Order 17 - Cask Design Study Final Report
[AREVA] Task Order 17 - Cask Design Study Final Report
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
[Energy Solutions] Task Order 17- Spent Nuclear Fuel Transportation Cask Design Study
[Energy Solutions] Task Order 17- Spent Nuclear Fuel Transportation Cask Design Study
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.
Everything You Ever Wanted to Know about Radioactive Waste Management
Everything You Ever Wanted to Know about Radioactive Waste Management
Explanation of Radioactivity and Radioactive waste