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Geological Disposal of Nuclear Waste
Geological Disposal of Nuclear Waste
19th Annual Symposium-Geological Disposal of Nuclear Waste
Geologic Factors in Nuclear Waste Disposal
Geologic Factors in Nuclear Waste Disposal
The study of geosciences and their relation to nuclear waste disposal and<br/>management entails analyzing the hydrology, chemistry, and geometry of the<br/>nuclear waste migration process. Hydrologic effects are determined by<br/>analyzing the porosity and permeability (natural and induced) of rock as well,<br/>as pressures and gradients, dispersion, and aquifer length of the system.<br/>Chemistry parameters include radionuclide retardation factors and waste<br/>dissolution rate.
The Department of Energy Does Not Plan to Use an Abandoned Salt Mine at Lyons, Kansas, for Nuclear High-Level Waste Disposal (EMD-82-64)
The Department of Energy Does Not Plan to Use an Abandoned Salt Mine at Lyons, Kansas, for Nuclear High-Level Waste Disposal (EMD-82-64)
Letter to The Honorable Nancy L. Kassebaum from J. Dexter Peach, Director, U.S. General Accounting Office
Regulations for Geological Disposal
Regulations for Geological Disposal
A Monitored Retrievable Storage Facility: Technical Background Information
A Monitored Retrievable Storage Facility: Technical Background Information
The U.S. Government is seeking a site for a monitored retrievable storage facility (MRS). Employing proven technologies used in this country and abroad, the MRS will be an integral part of the Federal system for safe and permanent disposal of the nation's high-level radioactive wastes. The MRS will accept shipments of spent fuel from commerical nuclear power plants, temporarily store the spent fuel above ground, and stage shipments of it to a geologic repository for permanent disposal.
Institutional Issues in the Planning and Implementation of a Program to Dispose of High-Level Radioactive Wastes
Institutional Issues in the Planning and Implementation of a Program to Dispose of High-Level Radioactive Wastes
The research reported here was initiated in January 1980 and performed for the Office of Policy and Evaluation, U.S. Department of Energy. The study arises from recognition by the DOE that the resolution of institutional issues is vital to the establishment of facilities to dispose of high-level radioactive waste (HLW). The disposal of HLW is an intensely difficult public policy problem.
DISPOSAL OF RADIOACTIVE WASTE: THE FORMING OF A NEW APPROACH IN GERMANY
DISPOSAL OF RADIOACTIVE WASTE: THE FORMING OF A NEW APPROACH IN GERMANY
Experimental Investigation of Burnup Credit for Safe Transport, Storage, and Disposal of Spent Nuclear Fuel
Experimental Investigation of Burnup Credit for Safe Transport, Storage, and Disposal of Spent Nuclear Fuel
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
Regulatory Perspective on Potential Fuel Reconfiguration and Its Implication to High Burnup Spent Fuel Storage and Transportation
Regulatory Perspective on Potential Fuel Reconfiguration and Its Implication to High Burnup Spent Fuel Storage and Transportation
The recent experiments conducted by Argonne National Laboratory on high burnup fuel cladding material property show that the ductile to brittle transition temperature of high burnup fuel cladding is dependent on: (1) cladding material, (2) irradiation conditions, and (3) drying-storage histories (stress at maximum temperature) [1]. The experiment results also show that the ductile to brittle temperature increases as the fuel burnup increases.
Burnup Credit - Technical Basis for Spent-Fuel Burnup Verification
Burnup Credit - Technical Basis for Spent-Fuel Burnup Verification
Present regulatory practices provide as much burnup credit flexibility as can be currently
expected. Further progress is achievable by incorporating the negative reactivity effects of a
subset of neutron-absorbing fission-product isotopes, and by optimizing the procedural approach
for establishing the burnup characteristics of the spent fuel to be loaded in burnup-creditdesigned
storage and transportation systems. This report describes progress toward developing a
Fission Product Experiment Program: Validation and Calculational Analysis
Fission Product Experiment Program: Validation and Calculational Analysis
From 1998 to 2004, a series of critical experiments referred to as the fission product (FP) experimental program was performed at the Commissariat à l'Energie Atomique Valduc research facility. The experiments were designed by Institut de Radioprotection et de Sûreté Nucléaire (IRSN) and funded by AREVA NC and IRSN within the French program supporting development of a technical basis for burnup credit validation.
Improved Radiochemical Assay Analyses Using TRITON Depletion Sequences in SCALE
Improved Radiochemical Assay Analyses Using TRITON Depletion Sequences in SCALE
Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), and Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants
Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), and Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants
The objective of this siting study work is to support DOE in evaluating integrated advanced nuclear plant and ISFSI deployment options in the future. This study looks at several nuclear power plant growth scenarios that consider the locations of existing and planned commercial nuclear power plants integrated with the establishment of consolidated interim spent fuel storage installations (ISFSIs).
BWR Axial Profile
BWR Axial Profile
Helping a Community Control its Future: Potential Negotiating Packages and Benefits for an MRS Host
Helping a Community Control its Future: Potential Negotiating Packages and Benefits for an MRS Host
The voluntary siting process for the Monitored Retrievable Storage (MRS) facility set forth in the Nuclear Waste Policy Amendments Act (NWPAA) of 1987 provides a potential host community a unique opportunity to improve its present situation and to gain greater control over its future.
Transportation and Storage Subcommittee Report to the Full Commission - Updated Report
Transportation and Storage Subcommittee Report to the Full Commission - Updated Report
To organize its investigation of whether changes are needed in the nation’s current approach to storing and eventually transporting spent nuclear fuel (SNF) and high-level waste (HLW), the Subcommittee began by asking a series of related questions:
• What role should storage play in an integrated U.S. waste management system and strategy in the future?
Benchmarks for Quantifying Fuel Reactivity Depletion Uncertainty
Benchmarks for Quantifying Fuel Reactivity Depletion Uncertainty
Analytical methods, described in this report, are used to
systematically determine experimental fuel sub-batch
reactivities as a function of burnup. Fuel sub-batch reactivities
are inferred using more than 600 in-core pressurized water
reactor (PWR) flux maps taken during 44 cycles of operation
at the Catawba and McGuire nuclear power plants. The
analytical methods systematically search for fuel sub-batch
reactivities that minimize differences between measured and
computed reaction rates, using Studsvik Scandpower’s
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.
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT FOURTH NATIONAL REPORT Argentina
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT FOURTH NATIONAL REPORT Argentina
The structure of the Fourth National Report complies with the Guidelines Regarding the
Form and Structure of National Reports (INFCIRC/604/Rev.1).
Section A describes the scope of the nuclear activity developed in Argentina since 1950
as well as the legal and regulatory framework. It also makes reference to the Strategic
Plan for Radioactive Waste Management (Strategic Plan), which refers to the safety of
Spent Fuel Management and Radioactive Waste Management.
Evaluating Site Suitability for a HLW Repository
Evaluating Site Suitability for a HLW Repository
The primary objective of government policy, and of NUMO in implementing this policy, is to
ensure that a repository for Japan’s high-level radioactive waste is located so as to provide
secure isolation of the waste and adequate safety for present and future generations. This
means that the site has to be chosen carefully, taking full account of all its characteristics. In
order to address these characteristics in an orderly and structured manner, we have established