Category of Content
Siting Experience Documents Only
Publication Date
Country
Keywords
Dissolved Concentration Limits of Elements with Radioactive Isotopes
Dissolved Concentration Limits of Elements with Radioactive Isotopes
The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments.
EPRI Review of Geologic Disposal for Used Fuel and High-Level Radioactive Waste: Volume III --Review of National Repository Programs
EPRI Review of Geologic Disposal for Used Fuel and High-Level Radioactive Waste: Volume III --Review of National Repository Programs
The effective termination of the Yucca Mountain program by the U.S. Administration in 2009
has left the U.S. program for management of used fuel and high level radioactive waste (HLW)
in a state of uncertainty. In concert with this major policy reset and in response to the resulting
policy vacuum, the President directed the Energy Secretary to establish the Blue Ribbon
Commission on America’s Nuclear Future (BRC) “…to conduct a comprehensive review of
policies for managing the back end of the nuclear fuel cycle and to provide recommendations for
EBS Radionuclide Transport Abstraction
EBS Radionuclide Transport Abstraction
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).
Waste Package Flooding Probability Evaluation
Waste Package Flooding Probability Evaluation
The objective of this calculation is to evaluate the probability of flooding a waste package with seepage water. Disruptive events can affect the Engineered Barrier System (EBS) components and have the potential to allow an advective flow of seepage water to reach the waste package. The advective and diffusive flow paths into the waste package have the potential to result in water accumulation inside the waste package, which in turn can lead to a potentially critical configuration. This calculation will evaluate the following:
Letter from the BRC to the Members of the South Carolina Congressional Delegation
Letter from the BRC to the Members of the South Carolina Congressional Delegation
Dear Members of the South Carolina Congressional Delegation:
Thank you all for your letter of October 27th. We appreciate hearing your views on the
Yucca Mountain project, the safety benefits of deep geologic disposal, and the
importance of the retaining the H Canyon facility at the Department of Energy’s
Savannah River Site.
In our draft report, the Commission finds that deep geologic disposal is an essential
component of a comprehensive nuclear waste management system. Your comments
Standards & Regulations for the Geologic Disposal of Spent Nuclear Fuel and High-Level Waste
Standards & Regulations for the Geologic Disposal of Spent Nuclear Fuel and High-Level Waste
This paper draws on my experience as a reviewer of the scientific programs and performance assessments of the geological repository for transuranic waste at the Waste Isolation Pilot Plant in New Mexico and the proposed repository for spent nuclear fuel and high-level waste at Yucca Mountain in Nevada. In addition, I have served on numerous committees of the National Research Council that have addressed many aspects of nuclear waste management.
Preliminary Criticality Analysis of Degraded SNF Accumulations External to a Waste Package (SCPB: N/A)
Preliminary Criticality Analysis of Degraded SNF Accumulations External to a Waste Package (SCPB: N/A)
This study is prepared by the Mined Geologic Disposal System (MODS) Waste Package Development Department (WPDD) to provide input to a separate evaluation on the probablility of criticality in the far- field environment. These calculations are performed in sufficient detail to provide conservatively bounding configurations to support separate probabilistic analyses.
In-Drift Precipitates/Salts Model
In-Drift Precipitates/Salts Model
This report documents the development and validation of the in-drift precipitates/salts (IDPS) process model. The IDPS process model is a geochemical model designed to predict the postclosure effects of evaporation and deliquescence on the chemical composition of water within the Engineered Barrier System (EBS) in support of the total system performance assessment (TSPA). Application of the model in support of TSPA is documented in Engineered Barrier System: Physical and Chemical Environment (BSC 2005 [DIRS 175083]).
Engineered Barrier System: Physical and Chemical Environment
Engineered Barrier System: Physical and Chemical Environment
The purpose of this model report is to describe the evolution of the physical and chemical environmental conditions within the waste emplacement drifts of the repository, including the drip shield and waste package surfaces. This report documents the development of a new process-level model, the near-field chemistry (NFC) model, and develops two abstraction models.
SCOPING STUDY OF SALT DOMES, BASALTS AND CRYSTALLINE ROCK AS RELATED TO LONG TERM RISK MODELING FOR DEEP GEOLOGIC DISPOSAL OF NUCLEAR WASTE
SCOPING STUDY OF SALT DOMES, BASALTS AND CRYSTALLINE ROCK AS RELATED TO LONG TERM RISK MODELING FOR DEEP GEOLOGIC DISPOSAL OF NUCLEAR WASTE
The purpose of this study is to provide a preliminary geotechnical data base sufficient to initiate the development of Long-Term Risk Models (LTRM), for salt domes, basalt and crystalline rock, and identify technical issues requiring additional investigation.
SUMMARY STATEMENT OF STEVE FRISHMAN
SUMMARY STATEMENT OF STEVE FRISHMAN
Radioactive Waste Management Programmes in OECD/NEA Member Countries: Sweden
Radioactive Waste Management Programmes in OECD/NEA Member Countries: Sweden
Summary of radioactive waste and management programs in Sweden, including national nuclear energy context; sources, types, and quantities of waste; radioactive waste management policies and programs; research and development; decommissioning and dismantling policies and projects; transport; authorities and implementing organizations; financing; and public information.
A Site is Selected
A Site is Selected
Web page from SKB's website (Swedish Nuclear Fuel and Waste Management Company), announcing that it has selected Forsmark, in the municipality of Östhammar, as the site for the final repository for Sweden's spent nuclear fuel.
Continuing Cooperation with Two Municipalities
Continuing Cooperation with Two Municipalities
Web page from SKB's website (Swedish Nuclear Fuel and Waste Management Company) discussing the ongoing cooperation between SKB and both Östhammar, where the repository is to be sited, and Oskarshamn, where the encapsulation plant is to be located.
The Cigéo Project: Meuse/Haute-Marne Reversible Geological Disposal Facility for Radioactive Waste
The Cigéo Project: Meuse/Haute-Marne Reversible Geological Disposal Facility for Radioactive Waste
Report prepared by ANDRA, the French National Radioactive Waste Management Agency, for preparing for public debate in 2013.
Dossier 2005: ANDRA Research on the Geological Disposal of High-Level Long-Lived Radioactive Waste: Summary
Dossier 2005: ANDRA Research on the Geological Disposal of High-Level Long-Lived Radioactive Waste: Summary
A summary of ANDRA's research into disposal of radioactive waste in a deep geologic repository, examining both clay and granite.
Dossier 2005: ANDRA Research on the Geological Disposal of High-Level Long-Lived Radioactive Waste: Results and Perspectives
Dossier 2005: ANDRA Research on the Geological Disposal of High-Level Long-Lived Radioactive Waste: Results and Perspectives
A report documenting ANDRA's research on deep disposal of radioactive waste, examining both clay and granite formations.
Cigéo, the French Geological Disposal Project
Cigéo, the French Geological Disposal Project
Presentation given by François-Michel Gonnot at the Stockholm Talks on October 2, 2013 regarding Cigéo, the French Geological Disposal Project.
Annual Sustainable Development and Activity Report - 2011
Annual Sustainable Development and Activity Report - 2011
Annual report by ANDRA, the French National Radioactive Waste Management Agency, regarding its activities in 2011.
Activity and Sustainable Development Report - 2010
Activity and Sustainable Development Report - 2010
Annual report produced by ANDRA, the French National Radioactive Waste Management Agency describing its activities in 2010.
ANDRA Newsletter #8
ANDRA Newsletter #8
Newsletter produced by ANDRA, the French National Radioactive Waste Management Agency.
ANDRA Newsletter #7
ANDRA Newsletter #7
Newsletter produced by ANDRA, the French National Radioactive Waste Management Agency.
ANDRA Newsletter #4
ANDRA Newsletter #4
Newsletter produced by ANDRA, the French National Radioactive Waste Management Agency.
ANDRA Newsletter #2
ANDRA Newsletter #2
Newsletter produced by ANDRA, the French National Radioactive Waste Management Agency.