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Slides - Development of a High-Level Radioactive Waste Regulatory Structure
Slides - Development of a High-Level Radioactive Waste Regulatory Structure
Presented to Blue Ribbon Commission on America's Nuclear Future
Geological Disposal of Nuclear Waste
Geological Disposal of Nuclear Waste
19th Annual Symposium-Geological Disposal of Nuclear Waste
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
Identifying remaining socio-technical challenges at the national level: Canada
Identifying remaining socio-technical challenges at the national level: Canada
This country report on Canada contributes to the InSOTEC research programme’s Work Package 1.1 which maps remaining socio-technical challenges to the implementation of geological disposal of radioactive waste in fourteen countries in the EU and North America (www.insotec.eu). The aim of this country report is to provide an overview of the current situation of geological disposal of High Level radioactive Waste (HLW) and Spent Nuclear Fuel (SNF) in Canada.
Geological Challenges in Radioactive Waste Isolation Third Worldwide Review
Geological Challenges in Radioactive Waste Isolation Third Worldwide Review
The first worldwide review of geological problems in radioactive waste isolation was published by the Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) in 1991 (Witherspoon, 1991). This review was a compilation of reports that had been submitted to a workshop held in conjunction with the 28th International Geological Congress that took place July 9Ð19, 1989, in Washington, D.C.
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.
Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste
Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste
Should High-Level Nuclear Waste be Disposed of at Geographically Dispersed Sites?
Should High-Level Nuclear Waste be Disposed of at Geographically Dispersed Sites?
Consideration of the technical feasibility of Yucca Mountain in Nevada as the site for a high-level nuclear<br/>waste repository has led to an intense debate regarding the economic, social, and political impacts of the<br/>repository.
Using Geologic Conditions and Multiattribute Decision Analysis to Determine the Relative Favorability of selected Areas for Siting a High-level Radioactive Waste Repository
Using Geologic Conditions and Multiattribute Decision Analysis to Determine the Relative Favorability of selected Areas for Siting a High-level Radioactive Waste Repository
A method is presented for determining the relative favorability<br/>of geologically complex areas for isolating high-level<br/>radioactive wastes. In applying the method to the northeastern region<br/>of the United States, seismieity and tectonic activity were the<br/>screening criteria used to divide the region into three areas of<br/>increasing seismotectonic risk. The following criteria, specified by<br/>the U.S.
Geologic and Hydrologic Characterization and Evaluation of the Basin and Range Province Relative to the Disposal of High-Level Radioactive Waste-Part III-Geologic and Hydrologic Evaluation
Geologic and Hydrologic Characterization and Evaluation of the Basin and Range Province Relative to the Disposal of High-Level Radioactive Waste-Part III-Geologic and Hydrologic Evaluation
This report describes the first phase in evaluating the<br/>geology and hydrology of the Basin and Range Province for<br/>potential suitability of geohydrologic environments for isolation<br/>of high-level radioactive waste.
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
Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks
Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks
A Statistical Method for Estimating the Net Uncertainty in the Prediction of k Based on Isotopic Uncertainties
A Statistical Method for Estimating the Net Uncertainty in the Prediction of k Based on Isotopic Uncertainties
Validation of SCALE-4 for Burnup Credit Applications
Validation of SCALE-4 for Burnup Credit Applications
In the past, criticality analysis of pressurized water reactor (PWR) fuel stored in racks and casks has assumed that the fuel is fresh with the maximum allowable initial enrichment. If credit is allowed for fuel burnup in the design of casks that are used in the transport of spent light water reactor fuel to a repository, the increase in payload can lead to a significant reduction in the cost of transport and a potential reduction in the risk to the public. A portion of the work has been performed at Oak Ridge National Laboratory (ORNL) in support of the U.S.
Federal Policy for the Disposal of Highly Radioactive Wastes from Commercial Nuclear Power Plans, An Historical Analysis
Federal Policy for the Disposal of Highly Radioactive Wastes from Commercial Nuclear Power Plans, An Historical Analysis
How to dispose of highly radioactive wastes from commercial nuclear power plants is a question that has remained unresolved in the face of rapidly changing technological, economic, and political requirements. In the three decades following World War II, 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.
PWR Radiochemical Assay Benchmarks Using SAS2H and CASMO
PWR Radiochemical Assay Benchmarks Using SAS2H and CASMO
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.
Investigation of Average and Pin-Wise Burnup Modeling of PWR Fuel
Investigation of Average and Pin-Wise Burnup Modeling of PWR Fuel
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.