slides - ISFSI Pad Design Issues
slides - ISFSI Pad Design Issues
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
The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor
criticality safety analyses be validated against experimental measurements. If credit for the negative
reactivity of the depleted (or spent) fuel isotopics is desired, it is necessary to benchmark
computational methods against spent fuel critical configurations. This report summarizes a portion
of the ongoing effort to benchmark away-from-reactor criticality analysis methods using critical
configurations from commercial pressurized-water reactors.
The purpose of this report is to develop and analyze the Engineered Barrier System (EBS) Radionuclide Transport Abstraction Model, consistent with Level I and Level II model validation, as identified in Technical Work Plan for: Near-Field Environment: Engineered Barrier System: Radionuclide Transport Abstraction Model Report (BSC 2006 [DIRS 177739]). The EBS Radionuclide Transport Abstraction (or RTA) is the conceptual model used in the Total System Performance Assessment (TSPA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ).
The Blue Ribbon Commission on America’s Nuclear Future (BRC) asked us to study whether
occupational safety and health conditions in today's U.S. nuclear industry are reasonably safe,
and if those conditions have improved since the Three Mile Island event in 1979. The BRC also
asked us to look to the future, to try to anticipate worker safety and health risks that should be
addressed by the industry, its government regulators and private watchdogs.
Over the eight weeks allotted, we performed a limited review of the literature and spoke with
This paper presents an assessment of the benefits for extended burnup credit in transporting
pressurized-water-reactor (PWR) spent nuclear fuel (SNF) in the United States. A prototypic 32-
assembly cask and the current regulatory guidance were used as bases for this assessment. By
comparing recently released PWR discharge data with actinide-only-based loading curves, this
evaluation shows that additional negative reactivity (through either increased credit for fuel burnup or
NRC initiated a research activity with the Center for Nuclear Waste Regulatory Analyses (CNWRA®) to develop a conceptual test plan for measuring the quantity of residual water remaining in a canister following vacuum drying to the criterion referenced in NUREG–1536 (NRC, 2010). The test plan will be used to help NRC assess options for independently performing an experimental program or to support engagements with industry or the Department of Energy should they undertake a similar effort.
Thirty spent fuel samples obtained from boiling-water-reactor (BWR) fuel pins have been
modeled at Oak Ridge National Laboratory using the SAS2H sequence of the SCALE code system.
The SAS2H sequence uses transport methods combined with the depletion and decay capabilities
of the ORIGEN-S code to estimate the isotopic composition of fuel as a function of its burnup
history. Results of these calculations are compared with chemical assay measurements of spent fuel
inventories for each sample. Results show reasonable agreement between measured and predicted
The Analysis of the Total System Life Cycle Cost (TSLCC) of the Civilian Radioactive Waste Management Program represents the Office of Civilian Radioactive Waste Management's most recent estimate of the costs to dispose of the Nations's spent nuclear fuel (SNF) and high-level radioactive waste (HLW). This TSLCC analysis projects all Program costs through 2119 for a surrogate, single potential repository. The design and emplacement concepts in this TSLCC analysis are the same as those presented in the Monitored Geologic Repository Project Description Document.
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Approximately 54,000 tons of spent nuclear fuel are stored at operating nuclear power plants and several decommissioned power plants throughout the country. Spent fuel storage at these sites was never intended to be permanent. The current Federal plan is to place the fuel in a repository for permanent disposal in Nevada at Yucca Mountain.
The objectives of this report are to document the development of data and assumptions used in
developing the transportation modules of the Total System Model (TSM) and to demonstrate that
transportation and transportation timing work correctly. This validation supports the
Transportation Design and Basis Report (BSC 2007a) and is issued with Version 6.0 of the TSM.
This report is largely based on the analysis approach and content in the transportation calculation
provided for TSM Version 4.0 (BSC 2006a). Much of the information in that report is repeated
The results of an extensive update of the decay data of the ORIGEN-S library are presented
in this report. The updated decay data were provided for both the ORIGEN-S and ORIGEN2
libraries in the same project. A complete edit of the decay data plus the available half-life
uncertainties are included in Appendix A. A detailed description of the types of data contained in the
library, the format of the library, and the data sources are also presented. Approximately 24% of the
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
An Account of the Programs of Federal Agencies and Events That Have Led to the Selection of a Potential Site for a Geologic Repository for High-Level Radioactive Waste
The benefits of burnup credit and the technical issues associated with utilizing burnup credit in spent
nuclear fuel (SNF) casks have been studied in the United States for almost two decades. The issuance of the
U.S. Nuclear Regulatory Commission (NRC) staff guidance for actinide-only burnup credit in 2002 was a
significant step toward providing a regulatory framework for using burnup credit in transport casks. However,
adherence to the current regulatory guidance (e.g., limit credit to actinides) enables only about 30% of the existing
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
The validity of the computation of pressurized-water-reactor (PWR) spent fuel isotopic
composition by the SCALE system depletion analysis was assessed using data presented in the report.
Radiochemical measurements and SCALE/SAS2H computations of depleted fuel isotopics were
compared with 19 benchmark-problem samples from Calvert Cliffs Unit 1, H. B. Robinson Unit 2,
and Obrigheim PWRs. Even though not exhaustive in scope, the validation included comparison of
predicted and measured concentrations for 14 actinides and 37 fission and activation products.
This report provides details of dry storage cask systems and contents in U.S. for commercial light water
reactor fuel. Section 2 contains details on the canisters used to store approximately 86% of assemblies in
dry storage in the U.S. Transport cask details for bare fuels, dual purpose casks and canister transport
casks are included in Section 3. Section 4 details the inventory of those shutdown sites without any
operating reactors. Information includes the cask type deployed, transport license and status as well as
Gentlemen,
In accordance with the charter of the Blue Ribbon Commission on America's Nuclear Future and as the Secretary's designee, I approve your request to establish an ad hoc subcommittee to review and make a recommendation to the Commission regarding the co-mingling of defense and commercial waste.
This letter also serves to appoint Dr. Allison Macfarlane as the chair of the subcommittee and the membership of the subcommittee as identified in your letter to me dated October 31, 2011.
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
The OECD Nuclear Energy Agency (NEA) Forum on Stakeholder Confidence (FSC) acts as a centre for informed exchange of knowledge and experience regarding stakeholder interaction and public participation in radioactive waste management. It promotes an open discussion among members and stakeholders, across institutional boundaries, and between technical and non-technical actors, in an atmosphere of trust and mutual respect. As such, the FSC is, first and foremost, a learning organisation.
Crystal River Unit 3 License Renewal Application being renewed by Florida Power Corporation, doing business as Progress Energy Florida, Inc.
This validation report supports the issuance of Version 6.0 of the Total System Model (TSM, BSC 2007a) that is described in the TSM User Manual (UM, BSC 2007b) and the TSM Preprocessor (TSMPP) User Manual (BSC 2007c). This report assumes the reader has detailed, working knowledge of the TSM functions and the Civilian Radioactive Waste Management System (CRWMS) operations. This report is based on an earlier document, Validation Report: Total System Model Version 5.0 Report Generators (BSC 2007d) that supported TSM Version 5.0.
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
The Connecticut Yankee Atomic Power Company (CY) today announced that the State of Connecticut’s Department of Environmental Protection (DEP) has approved CY’s application for a Stewardship Permit for its former plant site in Haddam CT. The approval marks a significant milestone in the decommissioning of the plant site.