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Development of Repository Concepts for Volunteer Siting Environments
Development of Repository Concepts for Volunteer Siting Environments
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 designed and located so as to provide secure isolation of the waste and adequate safety for present and future generations. This requires that the site of a repository has to be chosen carefully and an associated repository concept is selected which is appropriate for its specific geological and environmental conditions. At NUMO, we have chosen to implement a volunteering approach to siting.
Environmental Statement Radioactive Waste Repository, Lyons, Kansas, June 1971
Environmental Statement Radioactive Waste Repository, Lyons, Kansas, June 1971
As nuclear power assumes an increasingly important role in meeting the nation's requirements for electrical energy, the quantity of radioactive wastes will also increase. The wastes of primary concern -<br/>designated "high-level" and "alpha" wastes - contain radioactive nuclides that decay so slowly as to require that they be isolated from the biosphere for thousands of years.
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.
Geologic Disposal of Radioactive Waste - 1983
Geologic Disposal of Radioactive Waste - 1983
Geologic repositories for radioactive waste are evolving<br/>from conceptualization to the development of specific<br/>designs. Estimates of long-term hazards must be based<br/>upon quantitative predictions of environmental releases<br/>over time periods of hundreds of thousands of years and<br/>longer.
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.
How to Shape a Successful Repository Program: Staged Development of Geologic Repositories for High-level Waste
How to Shape a Successful Repository Program: Staged Development of Geologic Repositories for High-level Waste
Programs to manage and ultimately dispose of high-level radioactive wastes are unique from scientific and technological as well as socio-political aspects. From a scientific and technological perspective, high-level radioactive wastes remain potentially hazardous for geological time periods—many millennia—and scientific and technological programs must be put in place that result in a system that provides high confidence that the wastes will be isolated from the accessible environment for these many thousands of years.
Possible Strategies for Geoscientific Classification for High-Level Waste Repository Site Selection
Possible Strategies for Geoscientific Classification for High-Level Waste Repository Site Selection
This work was performed to suggest possible strategies for geoscientific classifications in the siting process of a high-level repository. To develop a feasible method for geoscientific classifications, a number of factors of a philosophical character, related to the purpose of the classifications, need to be accounted for. Many different approaches can be visualized, and this report was not intended to present a complete classification methodology.
General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories-Notice of Proposed Rulemaking (NOPR)
General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories-Notice of Proposed Rulemaking (NOPR)
Docket Number RW-RM-96-100, General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories-Notice of Proposed Rulemaking (NOPR)
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
Identifying remaining socio-technical challenges at the national level: USA
Identifying remaining socio-technical challenges at the national level: USA
This report contributes to the InSOTEC research programme’s Work Package 1.1 that maps remaining socio-technical challenges to the implementation of geological disposal of radioactive waste across fourteen countries in the EU and North America (www.insotec.eu). The aim of this 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 the USA.
Environmental Impact Statement, Management of Commercially Generated Radioactive Waste. Volume 1
Environmental Impact Statement, Management of Commercially Generated Radioactive Waste. Volume 1
In the course of producing electrical power in light water reactors (LWRs), the uranium
fuel accumulates fission products until the fission process is no longer efficient.for power
production. At that point the fuel is removed from the reactor and stored in water basins
to allow radioactivity to partially decay before further disposition. This fuel is referred
to as "spent fuel." Although spent fuel as it is discharged from a reactor is intensely
radioactive, it has been stored safely in moderate quantities for decades. Spent fuel could
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
The Report to the President and the Congress by the Secretary of Energy on the Need to a Second Repository
The Report to the President and the Congress by the Secretary of Energy on the Need to a Second Repository
The Nuclear Waste Policy Act of 1982, as amended (NWPA), establishes a process for the siting, construction and operation of one or more national repositories for permanent disposal of the Nation’s spent nuclear fuel (SNF) and high-level radioactive waste (HLW). In 1987, after the Department of Energy (the Department or DOE) had conducted studies of nine potential repository sites located throughout the United States, Congress amended the NWPA and selected the Yucca Mountain site in Nye County, Nevada as the only site for further study for the first national repository.
Recommendation by the Secretary of Energy of Candidate Sites for Site Characterization for the First Radioactive-Waste Repository
Recommendation by the Secretary of Energy of Candidate Sites for Site Characterization for the First Radioactive-Waste Repository
The Nuclear Waste Policy Act of 1982 (the Act), established a
step-by-step process for the siting of the nation's first repository for
high-level radioactive waste and spent fuel. The Act gave the Department of
Energy (DOE) the primary responsibility for conducting this siting process.
The first step in the process laid out in the Act was the development by
the DOE, with the concurrence of the Nuclear Regulatory Commission (NRC), of
general guidelines to be used by the Secretary of the DOE (the Secretary) in
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
BWR Axial Profile
BWR Axial Profile
Confidence in the Long-term Safety of Deep Geological Repositories--Its Development and Communication
Confidence in the Long-term Safety of Deep Geological Repositories--Its Development and Communication
Confidence in the long-term safety of deep geological disposal, and the ways in which this
confidence can be obtained and communicated, are topics of great importance to the radioactive waste
management community.1
The technical aspects of confidence have been the subject of considerable debate, especially
the concept of model validation. It has, for example, been pointed out that it is impossible to describe
fully the evolution of an open system, such as a repository and its environment, that cannot be
A Multiattribute Utility Analysis of Sites Nominated for Characterization for the First Radioactive-Waste Repository--A Decision-Aiding Methodology
A Multiattribute Utility Analysis of Sites Nominated for Characterization for the First Radioactive-Waste Repository--A Decision-Aiding Methodology
The Department of Energy (DOE), pursuant to the Atomic Energy Act of 1954
as amended, the Energy Reorganization Act of 1974, the Department of Energy
Organization Act of 1977, and the Nuclear Waste Policy Act of 1982 (the Act),
has the responsibility to provide for the disposal of high-level radioactive
waste and spent nuclear fuel.* The DOE selected mined geologic repositories
as the preferred means for the disposal of commercially generated high-level
radioactive waste and spent fuel (Federal Register, Vol. 46, p. 26677, May 14,
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
Locating a radioactive waste repository in the ring of fire
Locating a radioactive waste repository in the ring of fire
The scientific, technical, and sociopolitical challenges of finding a secure site for a geological repository for radioactive wastes have created a long and stony path for many countries. Japan carried out many years of research and development before taking its first steps in site selection.
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,
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.