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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
Radiolytic Specie Generation from Internal Waste Package Criticality
Radiolytic Specie Generation from Internal Waste Package Criticality
The Likelihood of Criticality Following Disposal of SF/HLW/HEU/Pu
The Likelihood of Criticality Following Disposal of SF/HLW/HEU/Pu
Supplement to the Disposal Criticality Analysis Methodology
Supplement to the Disposal Criticality Analysis Methodology
UNF-STANDARDS presentation to EPRI extended storage collaboration project
UNF-STANDARDS presentation to EPRI extended storage collaboration project
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).
Preclosure Criticality Analysis Process Report
Preclosure Criticality Analysis Process Report
The preclosure criticality analysis process described in this technical report provides a systematic approach for determining the need for criticality controls and for evaluating their effectiveness during the preclosure period of the Monitored Geologic Repository at Yucca Mountain, Nevada.
EQ6 Calculation for Chemical Degradation of Pu-Ceramic Waste Packages: Effects of Updated Materials Composition and Rates
EQ6 Calculation for Chemical Degradation of Pu-Ceramic Waste Packages: Effects of Updated Materials Composition and Rates
The Monitored Geologic Repository (MGR) Waste Package Operations (WPO) of the Civilian Radioactive Waste Management System Management and Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of Pu-ceramic waste forms. The Pu- ceramic (Refs. 1 and 2) is designed to immobilize excess plutonium from weapons production, and has been considered for disposal at the potential Yucca Mountain site.
Westinghouse MOX SNF Isotopic Source
Westinghouse MOX SNF Isotopic Source
The purpose of this calculation is to develop an estimate of the isotopic content as a function of time for mixed oxide (MOX) spent nuclear fuel (SNF) assemblies in a Westinghouse pressurized water reactor (PWR). These data will be used as source data for criticality, thermal, and radiation shielding evaluations of waste package (WP) designs for MOX assemblies in the Monitored Geologic Repository (MGR).
Criticality Model
Criticality Model
The Disposal Criticality Analysis Methodology Topical Report (YMP 2003) presents the methodology for evaluating potential criticality situations in the monitored geologic repository. As stated in the referenced Topical Report, the detailed methodology for performing the disposal criticality analyses will be documented in model reports. Many of the models developed in support of the Topical Report differ from the definition of models as given in the Office of Civilian Radioactive Waste Management procedure AP-SIII.10Q, Models, in that they are procedural, rather than mathematical.
NRC Waste Confidence Positions
NRC Waste Confidence Positions
In response to the remand of the U.S. Court of Appeals for the District of Columbia Circuit (Minnesota v. NRC, 602 F.2d 412 (1979)), and as a continuation of previous proceedings conducted in this area by NRC (44 Fed. Reg. 61,372), the Commission initiated a generic rulemaking proceeding on October 25, 1979.
Report to Congress on Reassessment of the Civilian Radioactive Waste Management Program
Report to Congress on Reassessment of the Civilian Radioactive Waste Management Program
The success of the Civilian Radioactive Waste Management Program of the U.S.
Department of Energy (DOE) is critical to U.S. ability to manage and dispose of
nuclear waste safely--and to the reestablishment of confidence in the nuclear energy
option in the United States. The program must conform with all applicable standards
and, in fact, set the example for a national policy on the safe disposal of radioactive
waste.
The Secretary of Energy has recently completed an extensive review of the
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
Intact and Degraded Mode Criticality Calculations for the Codisposal of TMI-2 Spent Nuclear Fuel in a Waste Package
Intact and Degraded Mode Criticality Calculations for the Codisposal of TMI-2 Spent Nuclear Fuel in a Waste Package
The objective of these calculations is to perform intact and degraded mode criticality evaluations of the Department of Energy's (DOE) Three Mile Island- Unit 2 (TMI-2) spent nuclear fuel (SNF) in canisters. This analysis evaluates codisposal in a 5-Defense High-Level Waste (5-DHLW/DOE SNF) Long Waste Package (Civilian Radioactive Waste Management System Management and Operating Contractor [CRWMS M&O] 2000b, Attachment V), which is to be placed in a potential monitored geologic repository (MGR).
Disposal Subcommittee Report to the Full Commission
Disposal Subcommittee Report to the Full Commission
The Disposal Subcommittee of the Blue Ribbon Commission on America’s Nuclear Future (BRC) addressed a wide-ranging set of issues, all bearing directly on the central question: “How can the United States go about establishing one or more disposal sites for high-level nuclear wastes in a manner and within a timeframe that is technically, socially, economically, and politically acceptable?”
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
EQ6 calculations for Chemical Degradation of Navy Waste Packages
EQ6 calculations for Chemical Degradation of Navy Waste Packages
The Monitored Geologic Repository Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Navy (Refs. 1 and , 2). The Navy SNF has been considered for disposal at the potential Yucca Mountain site. For some waste packages, the containment may breach (Ref. 3), allowing the influx of water. Water in the waste package may moderate neutrons, increasing the likelihood of a criticality event within the waste package.
slides - Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste
slides - Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
The Siting Record
The Siting Record
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
Federal Policy for the Disposal of Highly Radioactive Wastes from Commercial Nuclear Power Plants
Federal Policy for the Disposal of Highly Radioactive Wastes from Commercial Nuclear Power Plants
How to dispose of highly radioactive wastes from commercial nuclear power plants is a question that has remained unresolved in the face rapidly changing technological, economic, and political requirements. In the three decades following WWII, two federal agencies -- the Atomic Energy Commission and the Energy Research and Development Administration -- tried unsuccessfully to develop a satisfactory plan for managing high level wastes.
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
Management of Uncertainty in Safety Cases and the Role of Risk - Workshop Proceedings
Management of Uncertainty in Safety Cases and the Role of Risk - Workshop Proceedings
The development of radioactive waste repositories involves consideration of how the waste and the
engineered barrier systems will evolve, as well as the interactions between these and, often relatively
complex, natural systems. The timescales that must be considered are much longer than the timescales
that can be studied in the laboratory or during site characterisation. These and other factors can lead to
various types of uncertainty (on scenarios, models and parameters) in the assessment of long-term,
Radioactive Waste Disposal in Geological Formations International Conference Braunschweig ("City of Science 2007") November 6 – 9, 2007 Proceedings
Radioactive Waste Disposal in Geological Formations International Conference Braunschweig ("City of Science 2007") November 6 – 9, 2007 Proceedings
To solve the still open question of high-level radioactive waste disposal, the countries having made the greatest progress in this
field usually choose to carry out comparing selection procedures including broad involvement of the public. This is a central
result of the “RepoSafe”symposium which took place from November 6 to 9, 2007, in Braunschweig. Within the scope of
this symposium, internationally leading experts, invited by the Federal Office for Radiation Protection (BfS) and Gesellschaft
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Project Overview Report
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Project Overview Report
As outlined in the overall program for high-level waste (HLW) management in Japan, defined by the Atomic Energy Commission (AEC), HWL separated from spent nuclear fuel during reprocessing will be immobilized in a glass matrix and stored for a period of 30 to 50 years to allow cooling; it will then be disposed of in a stable deep geological formation.
History, Structure and Institutional Overview of the Nuclear Waste Policy Act of 1982
History, Structure and Institutional Overview of the Nuclear Waste Policy Act of 1982
The Nuclear Waste Policy Act of 1982 (NWPA) established a program to deal comprehensively with the waste byproducts of nuclear power generation, as well as defense-related radioactive wastes, if appropriate. Under this program, the federal Department of Energy (DOE) must locate and develop a site for disposal of high-level radioactive wastes in a geologic setting capable of isolating them from adverse public and environmental exposure for at least 10,000 and up to 100,000 years.