NFST Transportation Program Overview
NFST Transportation Program Overview
Slides - 2014 National Tranpsortation Stakeholders Forum, Bloomington, MN, May 13-15, 2104
Slides - 2014 National Tranpsortation Stakeholders Forum, Bloomington, MN, May 13-15, 2104
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).
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
Slides - National Tranpsortation Stakeholders Forum, Minneapolis, MN, May, 14, 2014
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.
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
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
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.
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 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.
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.
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).
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.
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
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
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.
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
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.
Explanation of Radioactivity and Radioactive waste
This paper explores the relationship between the national environmental movement and nuclear technology in relation to a local emergent group. The historical development of nuclear technology in this country has followed a path leading to continued fear and mistrust of waste management by a portion of the population. At the forefront of opposition to nuclear technology are people and groups endorsing environmental values.
Andras goal of Sustainability
The responsibility for the governance of Australia is shared by Australia's federal government (also known as the Commonwealth government) and the governments of the six states and two self governing territories. Responsibility for radiation health and safety in each State and Territory rests with the respective State/Territory government, unless the activity is carried out by a Commonwealth agency or a contractor to a Commonwealth agency; in those cases the activity is regulated by the Federal government (Commonwealth government of Australia).
Following the massive earthquake and resulting tsunami damage in March of 2011 at the Fukushima
Daiichi nuclear power plant in Japan, interest was amplified for what was done for recovery at the Three
Mile Island Unit 2 (TMI-2) in the United States following its meltdown in 1979. Many parallels could be
drawn between to two accidents. This paper presents the results of research done into the TMI-2 recovery
effort and its applicability to the Fukushima Daiichi cleanup. This research focused on three topics:
At the present time in Canada, high-level radioactive waste is accumulating in the form of irradiated, used fuel from research reactors and nuclear power generating stations. The used fuel bundles are kept in water-filled bays at each of the reactor sites. Because water is both a radiation barrier and an effective coolant, this system provides a safe means of storage. Used fuel is also safely stored above ground in dry concrete canisters in several Canadian locations.