slides - Certification/Licensing Approaches for High Burnup Spent Fuel
slides - Certification/Licensing Approaches for High Burnup 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
NRC/NEI, January 24, 2014 Public Meeting Presentations
Spent fuel transportation and storage cask designs based on a burnup credit approach must
consider issues that are not relevant in casks designed under a fresh-fuel loading assumption. For
example, the spent fuel composition must be adequately characterized and the criticality analysis
model can be complicated by the need to consider axial burnup variations. Parametric analyses are
needed to characterize the importance of fuel assembly and fuel cycle parameters on spent fuel
This report presents a comprehensive description of the post-closure radiological safety assess- ment of a repository for spent fuel (SF), vitrified high-level waste (HLW) from the reprocessing of spent fuel and long-lived intermediate-level waste (ILW), sited in the Opalinus Clay of the Zürcher Weinland in northern Switzerland. This assessment has been carried out as part of the technical basis for Project Entsorgungsnachweis1, which also includes a synthesis of informa- tion from geological investigations of the Opalinus Clay and a report on engineering feasibility.
DOE decided to terminate the Yucca Mountain repository program because, according to DOE officials, it is not a workable option and there are better solutions that can achieve a broader national consensus. DOE did not cite technical or safety issues. DOE also did not identify alternatives, but it did create a Blue Ribbon Commission to evaluate and recommend alternatives.
This evaluation investigates the potential benefits of separating the transuranic elements from spent reactor fuel before it is disposed of in geologic repositories. It addresses the question: Would the benefits to radioactive waste disposal justify both processing the spent fuel and deploying liquid metal reactors (LMRs) to transmute the separated transuranics?
http://www.epri.com/abstracts/Pages/ProductAbstract.aspx?ProductId=NP-7…
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
This report investigates trends in the radiological decay properties and changes in relative nuclide importance associated with increasing enrichments and burnup for spent LWR fuel as they affect the areas of criticality safety, thermal analysis (decay heat), and shielding analysis of spent fuel transport and storage casks. To facilitate identifying the changes in the spent fuel compositions that most directly impact these application areas, the dominant nuclides in each area have been identified and ranked by importance.
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 presents studies performed to support the development of a technically justifiable approach for
addressing the axial-burnup distribution in pressurized-water reactor (PWR) burnup-credit criticality
safety analyses. The effect of the axial-burnup distribution on reactivity and proposed approaches for
addressing the axial-burnup distribution are briefly reviewed. A publicly available database of profiles is
examined in detail to identify profiles that maximize the neutron multiplication factor, keff, assess its
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
The Blue Ribbon Commission staff requested this paper cataloging innovative stakeholder involvement programs within the Department of Energy (DOE). I reviewed a variety of material on public involvement, including papers and presentations on stakeholder involvement in DOE programs, published presentations and comments to the BRC, and research reports on stakeholder and public involvement.
After more than 20 years of commercial nuclear power, the Federal Government has yet to develop a broadly supported policy for fulfilling its legal responsibility for the final isolation of high-level radioactive waste. OTA's study concludes that until such a policy is adopted in law, there is a substantial risk that the false starts, shifts of policy, and fluctuating support that have plagued the final isolation program in the past will continue.
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
The purpose of this report, and the information contained in the associated computerized data bases, is to establish the DOE/OCRWM reference characteristics of the radioactive waste materials that may be accepted by DOE for emplacement in the mined geologic disposal system as developed under the Nuclear Waste Policy Act of 1982. This report provides relevant technical data for use by DOE and its supporting contractors and is not intended to be a policy document.
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
The "Summary Report of Commercial Reactor Criticality Data for Sequoyah Unit 2" contains the detailed information necessary to perform commercial reactor criticality (CRC) analyses for the Sequoyah Unit 2 reactor.
The U.S. Department of Energy (DOE) submitted to the Nuclear Regulatory Commission (NRC) the Dry Transfer System (DTS) Topical Safety Analysis Report (TSAR) on
The Nuclear Waste Policy Act of 1982, as amended, established a statutory basis
for managing the nation’s civilian (or commercially produced) spent nuclear
fuel. The law established a process for siting, developing, licensing, and constructing
an underground repository for the permanent disposal of that waste.
Utilities were given the primary responsibility for storing spent fuel until it is
accepted by the Department of Energy (DOE) for disposal at a repository —
originally expected to begin operating in 1998. Since then, however, the repository
At the request of the U.S. Congress, the National Academies assessed the safety and
security of spent nuclear fuel stored in pools and dry casks at commercial nuclear power
plants in the United States. The public report can be viewed on the National Academies
Press website at http://books.nap.edu/catalog/11263.html.
In the November 1989 Report to Congress on Reassessment of the Civilian
Radioactive Waste Management Program (DOE/RW-0247), the Secretary of Energy
announced an initiative for developing a monitored retrievable storage (MRS) facility
that is to start spent-fuel acceptance in 1998. This facility, which will be licensed by
the U.S. Nuclear Regulatory Commission (NRC), will receive spent fuel from
commercial nuclear power plants and provide a limited amount of storage for this
This is the Nuclear Fuels Storage and Transportation Project Director's presentation on Near Term Planning for Stroage and Transportation of Used Nuclear Fuel presented to the Institute of Nuclear Materials Management on January 14, 2013 in Arlington Va.
The "Summary Report of SNF Isotopic Comparisons for the Disposal Criticality Analysis Methodology" contains a summary of the analyses that compare SNF measured isotopic concentrations (radiochemical assays) to calculated SNF isotop~c concentrations (SAS2H module ·orScale4.3). The results of these analyses are used to support the validation of the isotopic models for spent commercial light water reactor (LWR) fuel.
Background To determine whether current and former construction workers are at
significant risk for occupational illnesses from work at the Department of Energy’s (DOE)
nuclear weapons facilities, screening programs were undertaken at the Hanford Nuclear
Reservation, Oak Ridge Reservation, and the Savannah River Site.