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Features, Events, and Processes for the Total System Performance Assessment: Analyses
Features, Events, and Processes for the Total System Performance Assessment: Analyses
The purpose of this analysis report is to document the screening decisions and technical bases for inclusion or exclusion of each FEP identified as relevant to the TSPA and the Yucca Mountain disposal system, in accordance with the regulatory screening criteria identified for the Yucca Mountain Site.
Waste Package Misload Probability
Waste Package Misload Probability
The objective of this calculation is to calculate the probability of occurrence for fuel assembly (FA) misloads (i.e., FA placed in the wrong location) and FA damage during FA movements. The scope of this calculation is provided by the information obtained from the Framatome ANP 2001a report. The first step in this calculation is to categorize each fuel-handling event that occurred at nuclear power plants. The different categories are based on FAs being damaged or misloaded. The next step is to determine the total number of FAs involved in the event.
Parametric Study of the Effect of Burnable Poison Rods for PWR Burnup Credit
Parametric Study of the Effect of Burnable Poison Rods for PWR Burnup Credit
The Interim Staff Guidance on burnup credit (ISG-8) issued by the United States Nuclear Regulatory
Commission’s (U.S. NRC) Spent Fuel Project Office recommends restricting the use of burnup credit to
assemblies that have not used burnable absorbers. This recommended restriction eliminates a large portion
of the currently discharged spent fuel assemblies from cask loading, and thus severely limits the practical
usefulness of burnup credit. In the absence of readily available information on burnable poison rod (BPR)
Disposal Criticality Analysis Methodology Technical report
Disposal Criticality Analysis Methodology Technical report
The United States Department of Energy (DOE) is developing a postclosure methodology for criticality analysis to evaluate disposal of commercial spent nuclear fuel and other high-level waste in a geologic repository. A topical report on the postclosure disposal criticality analysis methodology is scheduled to be submitted to the United States Nuclear Regulatory Commission (NRC) for formal review in 1998 (to be verified). This technical report is being issued to describe the current status of the postclosure methodology development effort.
BWR Axial Profile
BWR Axial Profile
The purpose of this calculation is to develop axial profiles for estimating the axial variation in burnup of a boiling water reactor (BWR) assembly spent nuclear fuel (SNF) given the average burnup of an assembly. A discharged fuel assembly typically exhibits higher burnup in the center and lower burnup at the ends of the assembly. Criticality safety analyses taking credit for SNF burnup must account for axially varying burnup relative to calculations based on uniformly distributed assembly average burnup due to the under-burned tips.
Nuclear Waste Policy Act of 1982
Nuclear Waste Policy Act of 1982
An Act to provide for the development of repositories for the disposal of high-level radioactive waste and spent nuclear fuel, to establish a program of research, de- velopment, and demonstration regarding the disposal of high-level radioactive waste and spent nuclear fuel, and for other purposes.
Analysis of Mechanisms for Early Waste Package / Drip Shield Failure
Analysis of Mechanisms for Early Waste Package / Drip Shield Failure
The purpose of this analysis is to evaluate the types of defects or imperfections that could occur in a waste package or a drip shield and potentially lead to its early failure, and to estimate a probability of undetected occurrence for each type. An early failure is defined as the through-wall penetration of a waste package or drip shield due to manufacturing or handling-induced defects, at a time earlier than would be predicted by mechanistic degradation models for a defect-free waste package or drip shield.
Fast Flux Test Facility (FFTF) Reactor Fuel Degraded Criticality Calculation: Degraded SNF Canister
Fast Flux Test Facility (FFTF) Reactor Fuel Degraded Criticality Calculation: Degraded SNF Canister
The objective of this calculation is to characterize the criticality aspect of a Department of Energy Spent Nuclear Fuel (DOE SNF) canister containing 5 Fast Flux Test Facility (FFTF) assemblies in a Five-Pack defense High-Level Waste (HLW) waste package. The purpose of this calculation is to investigate the criticality issues for the waste package (WP) containing HLW and DOE SNF canisters in various stages of degradation.
Intact and Degraded Mode Criticality Calculations for the Codisposal of ATR Spent Nuclear Fuel in a Waste Package
Intact and Degraded Mode Criticality Calculations for the Codisposal of ATR Spent Nuclear Fuel in a Waste Package
The objective of this calculation is to perform intact and degraded mode criticality evaluations of the U.S. Department of Energy’s (DOE) Advanced Test Reactor (ATR) Spent Nuclear Fuel (SNF) placed in the DOE standardized SNF canister. This analysis evaluates the codisposal of the DOE SNF canister containing the ATR SNF in a 5-Defense High-Level Waste (5-DHLW) Short Waste Package (WP) (Bechtel SAIC Company, LLC [BSC] 2004a), which is to be placed in a monitored geologic repository (MGR).
Commercial Reactor Criticality Depletion For Grand Gulf, Unit 1
Commercial Reactor Criticality Depletion For Grand Gulf, Unit 1
The objectie of this calculation is to document the Grand Gulf, Unit 1, (GG1) fuel depletion calculations. The GG1 reactor is a boiling water reactor (BWR) owned and operated by Entergy Operations Inc. The Commercial Reactor Criticality (CRC) evaluations support the development and validation of the neutronic models used for criticality analyses involving commercial spent nuclear fuel in a geologic repository. This calculation is performed as part of the evaluation CRC program. This report is an engineering calculation supporting the burnup credit methodology of YMP 2000 (Ref.
Commercial Spent Nuclear Fuel Waste Package Misload Analysis
Commercial Spent Nuclear Fuel Waste Package Misload Analysis
The purpose of this calculation is to estimate the probability of misloading a commercial spent
nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or
burnup) outside the waste package design. The waste package designs are based on the expected
commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1
and Table 1). For this calculation, a misloaded waste package is defined as a waste package that
Nuclear Criticality Calculations for Canister-Based Facilities - Commercial SNF
Nuclear Criticality Calculations for Canister-Based Facilities - Commercial SNF
The purpose of this calculation is to perform waste-form specific nuclear criticality safety calculations to aid in establishing criticality safety design criteria, and to identify design and process parameters that are potentially important to the criticality safety of the transportation, aging and disposal (TAD) canister-based systems.
Wyoming Decline of MRS
Wyoming Decline of MRS
This letter is written by Former Wyoming Governor Mike Sullivan to inform the Fremont County Commissioners of his conclusion to decline the MRC facility.
Qualification of Thermodynamic Data for Geochemical Modeling of Mineral–Water Interactions in Dilute Systems
Qualification of Thermodynamic Data for Geochemical Modeling of Mineral–Water Interactions in Dilute Systems
This report is developed from Technical Work Plan for: Thermodynamic Databases for Chemical Modeling (BSC 2006 [DIRS 177885]). The purpose of this analysis report is to update the thermochemical database data0.ymp.R4 (Output DTN: SN0410T0510404.002). Various data have been added, corrected, or corroborated, partly in response to four Condition Reports (CRs): CR 6489, CR 6731, CR 7542, and CR 7756. The most notable changes are a general revision of phosphate data to achieve consistency with the recommendations from the Committee on Data for Science and Technology (CODATA) (Cox. et al.
Closing Yucca Mountain: Litigation Associated with Attempts to Abandon the Planned Nuclear Waste Repository
Closing Yucca Mountain: Litigation Associated with Attempts to Abandon the Planned Nuclear Waste Repository
Passed in 1982, the Nuclear Waste Policy Act (NWPA) was an effort to establish an explicit statutory basis for the Department of Energy (DOE) to dispose of the nation’s most highly radioactive nuclear waste. The NWPA requires DOE to remove spent nuclear fuel from commercial nuclear power plants, in exchange for a fee, and transport it to a permanent geologic repository or an interim storage facility before permanent disposal. Defense-related high-level<br>waste is to go into the same repository.
Screening and Identification of Sites for a Proposed Monitored Retreivable Storage Facilty
Screening and Identification of Sites for a Proposed Monitored Retreivable Storage Facilty
The Director, Office of Civilian Radioactive Waste Management (OCRWM), Department of Energy (DOE), has identified the Clinch River Breeder Reactor site, the DOE Oak Ridge Reservation and the Tennessee Valley Authority (TVA) Hartsville Nuclear Plant site as preferred and alternative sites, respectively, for development of site-specific designs as part of the proposal for construction of an integrated Monitored Retrievable Storage (MRS) Facility. The proposal, developed pursuant to Section 141(b) of the Nuclear Waste Policy Act of 1982, will be submitted to Congress in January 1986.
RETHINKING THE CHALLENGE OF HIGH-LEVEL NUCLEAR WASTE: Strategic Planning for Defense High-Level Waste and Spent Fuel Disposal
RETHINKING THE CHALLENGE OF HIGH-LEVEL NUCLEAR WASTE: Strategic Planning for Defense High-Level Waste and Spent Fuel Disposal
Disposal of High-Level Radioactive Wastes in a Proposed Geologic Repository at Yucca Mountain, Nevada; Final Rule
Disposal of High-Level Radioactive Wastes in a Proposed Geologic Repository at Yucca Mountain, Nevada; Final Rule
The Nuclear Regulatory Commission (NRC) is publishing licensing criteria for disposal of spent nuclear fuel and high-level radioactive wastes in the proposed geologic repository at Yucca Mountain, Nevada. As mandated by law, this final rule changes the Commissions technical requirements and criteria, as necessary, to be consistent with final environmental standards for Yucca Mountain issued by the U.S. Environmental Protection Agency (EPA).
Local Liaison Committees and National Association of Local Liaison Committees: the French experience
Local Liaison Committees and National Association of Local Liaison Committees: the French experience
In the context of the governance of nuclear activities, especially in the field of the radioactive waste management, the self-structuring of civil society is a necessary condition of the citizens’ action. The experience of French “Commissions Locales d’Information” (CLIs) and their national federation the “Association Nationale des Commissions Locales d’Information” (ANCLI) represent an interesting and original example of local actors empowerment. In France, Local Information Commissions (CLI) are attached to most of the nuclear sites.
MAKING CONSULTATION AND CONCURRENCE WORK
MAKING CONSULTATION AND CONCURRENCE WORK
Two Citizen Task Forces and the Challenge of the Evolving Nuclear Waste Siting Process
Two Citizen Task Forces and the Challenge of the Evolving Nuclear Waste Siting Process
Siting any nuclear waste facility is problematic in today's climate of distrust toward nuclear agencies and fear of nuclear waste. This study compares and contrasts the siting and public participation processes as two citizen task forces dealt with their difficult responsibilities. Though one dealt with a high level waste (Monitored Retrievable Storage - MRS) proposal in Tennessee in 1985-6 and the other with a proposed low level waste facility in Illinois (1988 and still ongoing), the needs of citizen decision makers were very similar.
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