slides - Deep Borehole Disposal of Spent Fuel
slides - Deep Borehole Disposal of Spent Fuel
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
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
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.
Nuclear Fuels Storage and Transportation Planning Project (NFST) Overview Presentation, 2014 Fuel Cycle Technologies (FCT) Annual Meeting, November 4-6, 2014, Idaho Falls, ID
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).
The purpose of this study is to analyze the costs and risks associated with transporting spent fuel by barge. The barge movements would be made in combination with rail movements to transport spent fuel from plants to a repository. For the purposes of this analysis, three candidate repository sites are analyzed: Yucca Mountain, Nevada, Deaf Smith, Texas, and Hanford, Washington. This report complements a report prepared by Sandia National Laboratories in 1984 that analyzes the costs and risks of transporting spent
fuel by rail and by truck to nine candidate repository sites.
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.
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
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
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.
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.
In the past, criticality analysis of pressurized water reactor (PWR) fuel stored in racks and casks has assumed that the fuel is fresh with the maximum allowable initial enrichment. If credit is allowed for fuel burnup in the design of casks that are used in the transport of spent light water reactor fuel to a repository, the increase in payload can lead to a significant reduction in the cost of transport and a potential reduction in the risk to the public. A portion of the work has been performed at Oak Ridge National Laboratory (ORNL) in support of the U.S.
The recent experiments conducted by Argonne National Laboratory on high burnup fuel cladding material property show that the ductile to brittle transition temperature of high burnup fuel cladding is dependent on: (1) cladding material, (2) irradiation conditions, and (3) drying-storage histories (stress at maximum temperature) [1]. The experiment results also show that the ductile to brittle temperature increases as the fuel burnup increases.
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).
To organize its investigation of whether changes are needed in the nation’s current approach to storing and eventually transporting spent nuclear fuel (SNF) and high-level waste (HLW), the Subcommittee began by asking a series of related questions:
• What role should storage play in an integrated U.S. waste management system and strategy in the future?
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay.
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay.
The U.S. Nuclear Regulatory Commission (NRC) is responsible for issuing regulations for the
packaging of spent fuel (and other large quantities of radioactive material) for transport that
provide for public health and safety during transport (Title 10 of the Code of Federal Regulations
(10 CFR) Part 71, “Packaging and Transportation of Radioactive Waste,” dated
January 26, 2004). In September 1977, the NRC published NUREG-0170, “Final Environmental
Statement on the Transportation of Radioactive Material by Air and Other Modes,” which
This Interim Staff Guidance (ISG) provides guidance to the staff for determining if
storage systems to be licensed under 10 CFR Part 72 allow ready retrieval of spent fuel.
This guidance is not a regulation or a requirement.