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Analysis of Critical Benchmark Experiments for Configurations External to WP
Analysis of Critical Benchmark Experiments for Configurations External to WP
The Disposal Criticality Analysis Methodology Topical Report (Reference 1) states that the accuracy of the criticality analysis methodology (MCNP Monte Carlo code and cross-section data) designated to assess the potential for criticality of various configurations in the Yucca Mountain proposed repository is established by evaluating appropriately selected benchmark critical experiments.
Long-Term Criticality Control Issues for the MPC (SCPB: N/A)
Long-Term Criticality Control Issues for the MPC (SCPB: N/A)
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) in response to a request received via a QAP-3-12 Design Input Data Request (Reference 5.1) from Waste Acceptance, Storage, & Transportation (WAST) Design (formerly MRSMPC Design). This design analysis is an answer to the Design Input Data Request to provide: Specific requirements for long-term criticality control.
Characteristics of Potential Repository Wastes
Characteristics of Potential Repository Wastes
The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for all spent fuels and high-level wastes (HLW) that will eventually be disposed of in a geologic repository. The purpose of this document, and the information contained in the associated computerized data bases and supporting technical reports, is to provide the technical characteristics of the radioactive waste materials that will (or may) be accepted by DOE for interim storage in an MRS or emplacement in a repository as developed under the Nuclear Waste Policy Act Amendment of 1987.
Transportation and Storage Subcommittee Report to the Full Commission DRAFT
Transportation and Storage Subcommittee Report to the Full Commission DRAFT
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 permanent disposal facilities are established.
To answer this question and to develop specific recommendations and options for consideration by the
full Commission, the Subcommittee held multiple meetings and deliberative sessions, visited several
Co-Mingled and Defense-Only Repositories
Co-Mingled and Defense-Only Repositories
At the request of the staff to the Blue Ribbon Commission on America’s Nuclear Future (“BRC”), we have reviewed the following questions:
1. Is there legal authority for DOE or any other entity to undertake to site a repository for “co-mingled” nuclear materials (i.e., civilian and defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW)) at any site other than Yucca Mountain?
Bias Determination for DOE Nuclear Fuels
Bias Determination for DOE Nuclear Fuels
The purpose of this calculation is to establish the relative change in the effective neutron multiplication factor (k-eff) due to the use of MCNP unique identifiers used in the paper, Nuclear Criticality Calculations for Canister-Based Facilities - DOE SNF, that are different from the MCNP unique identifiers used in the paper, Analysis of Critical Benchmark Experiments and Critical Limit Calculation for DOE SNF.
slides - Observations on Key Storage and Transport Technical Issues
slides - Observations on Key Storage and Transport Technical Issues
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Draft Report for Comment: Identification and Prioritization of the Technical Information Needs Affecting Potential Regulation of Extended Storage and Transportation of Spent Nuclear Fuel
Draft Report for Comment: Identification and Prioritization of the Technical Information Needs Affecting Potential Regulation of Extended Storage and Transportation of Spent Nuclear Fuel
he U.S. Nuclear Regulatory Commission (NRC) regulates storage of spent nuclear fuel (SNF) from commercial nuclear power plants. An increasing amount of the SNF in storage is in dry storage systems, mostly at current and decommissioned plants. As directed by the Commission (in SRM-COMSECY-10-0007; December 6, 2010), in expectation of continued use of dry storage for extended periods of time, the NRC staff is examining the technical needs and potential changes to the regulatory framework that may be needed to continue licensing of SNF storage over periods beyond 120 years.
Background Paper on Commingling of Defense and Commercial Waste
Background Paper on Commingling of Defense and Commercial Waste
Since a 1985 decision by President Reagan that a separate permanent repository for disposal of
defense high level waste was not required1, DOE has planned for disposal of all high-level waste
and spent fuel from national defense activities and DOE’s own research activities in a repository
for commercial waste developed under the Nuclear Waste Policy Act (NWPA). The Commission
has heard recommendations from some commenters2 that this decision be revisited, or even
Dose Rate Calculations for the 2-MCO/2-DHLW Waste Package
Dose Rate Calculations for the 2-MCO/2-DHLW Waste Package
Distribution of Characteristics of LWR Spent Fuel
Distribution of Characteristics of LWR Spent Fuel
The Materials Characterization Center (MCC) at Battelle Pacific Northwest Laboratory (PNL) has the responsibility to select appropriate spent fuel Approved Testing Materials (ATMs) and to characterize, via hot-cell studies, certain detailed properties of the discharged fuel. The purpose of this report isto develop a collective description of the entire spent fuel inventory in terms of various fuel properties relevant to ATMs using information available from the Characteristics Data Base (CDB), which is sponsored by the U.S.
Memo to Timothy Collins from Laurence Kopp - Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light-Water Reactor Power Plants
Memo to Timothy Collins from Laurence Kopp - Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light-Water Reactor Power Plants
Guidance concerning regulatory requirements for criticality analysis of new and spent fuel storage at light-water reactor power plants used by the Reactor Systems Branch.
Canister Handling Facility Criticality Safety Calculations
Canister Handling Facility Criticality Safety Calculations
This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC (Bechtel SAIC Company) 2004 (DIRS 167614).
Waste Package Filler Material Testing Report
Waste Package Filler Material Testing Report
As part of the Mined Geologic Disposal System Waste Package Development design activities, it has been determined that it may be beneficial to add material to fill the otherwise free spaces remaining in waste package after loading high-level nuclear waste. The use of filler material will benefit criticality control in spent nuclear fuel waste packages, by the moderator displacement method.
Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase II Degraded Codisposal Waste Package Internal Criticality
Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase II Degraded Codisposal Waste Package Internal Criticality
This report presents the analysis and conclusions with respect to disposal criticality for canisters containing aluminum-based fuels from research reactors. The analysis has been divided into three phases. Phase I, dealt with breached and flooded waste packages containing relatively intact canisters and intact internal (basket) structures; Phase II, the subject of this report, covers the degradation of the spent nuclear fuel (SNF) and structures internal to the codisposal waste package including high level waste (HLW), canisters, and critically control material.
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation--ARIANE and REBUS Programs (UO2 Fuel)
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation--ARIANE and REBUS Programs (UO2 Fuel)
This report is part of a report series designed to document benchmark-quality radiochemical assay data
against which computer code predictions of isotopic composition for spent nuclear fuel can be validated
to establish the uncertainty and bias associated with the code predictions. The experimental data analyzed
in the present report were acquired from two international programs: (1) ARIANE and (2) REBUS, both
coordinated by Belgonucleaire. All measurements include extensive actinide and fission product data of
Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel
Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel
Nuclear Wastes: Technologies for Separations and Transmutation
Nuclear Wastes: Technologies for Separations and Transmutation
Disposal of radioactive waste from nuclear weapons production and power generation has
caused public outcry and political consternation. Nuclear Wastes presents a critical review
of some waste management and disposal alternatives to the current national policy of
direct disposal of light water reactor spent fuel. The book offers clearcut conclusions for
what the nation should do today and what solutions should be explored for tomorrow.
The committee examines the currently used "once-through" fuel cycle versus different
Yankee Companies Urge Federal Government to Remove Used Nuclear Fuel in Wake of Favorable Federal Court Decision
Yankee Companies Urge Federal Government to Remove Used Nuclear Fuel in Wake of Favorable Federal Court Decision
U.S Court of Federal Claims Senior Judge James F. Merow issued a favorable ruling on September 30, 2006 for the three former Yankee nuclear power plants in their litigation with the federal government over its failure to remove used nuclear fuel from the three New England sites. Yankee Vice- President and Chief Financial Officer Michael Thomas said, “While the Court’s decision will need to be reviewed and evaluated, the Yankee companies’ initial reaction to the monetary award is very positive.
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.
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.
Intact and Degrade Mode Criticality Calculations for the Codisposal of TMI-2 Spent Nuclear Fuel in a Waste Package
Intact and Degrade Mode Criticality Calculations for the Codisposal of TMI-2 Spent Nuclear Fuel in a Waste Package
SOCIAL DISTRUST: IMPLICATIONS AND RECOMMENDATION FOR SPENT NUCLEAR FUEL AND HIGH LEVEL RADIOACTIVE WASTE MANAGEMENT
SOCIAL DISTRUST: IMPLICATIONS AND RECOMMENDATION FOR SPENT NUCLEAR FUEL AND HIGH LEVEL RADIOACTIVE WASTE MANAGEMENT
The management of spent nuclear fuel (SNF) and defense high level waste (HLW) is a complex sociotechnical
systems challenge. Coordinated, reliable, and safe performance will be required over very long
periods of time within evolving social and technical contexts. To accomplish these goals, a waste
management system will involve a host of facilities for interim storage and longterm disposal, a
transportation infrastructure, and research and development centers. The complexity of SNF and HLW