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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.
LINE - Leadership in Nuclear Energy Commission - Full Report
LINE - Leadership in Nuclear Energy Commission - Full Report
Recognizing that Idaho has a major strategic and economic interest in maintaining INL’s leadership role and in helping
the nuclear energy industry successfully meet these broader challenges, Idaho governor C.L. “Butch” Otter established
the Leadership in Nuclear Energy or “LINE” Commission in February 2012.
The Governor recognized that recent national developments in the nuclear energy sector will cause the State of Idaho to
face important choices in the future and that he needed to understand the best options available.
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).
Impacts Associated with Transfer of Spent Nuclear Fuel from Spent Fuel Storage Pools to Dry Storage After Five Years of Cooling
Impacts Associated with Transfer of Spent Nuclear Fuel from Spent Fuel Storage Pools to Dry Storage After Five Years of Cooling
In order to decrease the risk of terrorism, it has been suggested that used nuclear fuel should be
moved to dry storage early, after five years cooling in the spent fuel pool. The Nuclear
Regulatory Commission (NRC) has reviewed this issue and issued a white paper stating that it
did not believe such a measure was justified in light of additional security measures implemented
at nuclear plants and the impacts associated with the early movement of used fuel into dry
Spent Nuclear Fuel Discharges from U.S. Reactors 1994
Spent Nuclear Fuel Discharges from U.S. Reactors 1994
The International Security Implications Of U.S. Domestic Nuclear Power Decisions
The International Security Implications Of U.S. Domestic Nuclear Power Decisions
The United States makes decisions regarding the domestic uses of nuclear energy and the nuclear fuel cycle primarily based economic considerations, domestic political constraints, and environmental impact concerns. Such factors influence U.S. foreign policy decisions as well, but foreign policy decisions are often more strongly determined by national security considerations, including concerns about nuclear weapons proliferation and nuclear terrorism.
A Technology Roadmap for Generation IV Nuclear Energy Systems
A Technology Roadmap for Generation IV Nuclear Energy Systems
To advance nuclear energy to meet future energy needs, ten countries—Argentina, Brazil, Canada, France, Japan, the Republic of Korea, the Republic of South Africa, Switzerland, the United Kingdom, and the United States—have agreed on a framework for international cooperation in research for a future generation of nuclear energy systems, known as Generation IV. The figure below gives an overview of the generations of nuclear energy systems. The first generation was advanced in the 1950s and 60s in the early prototype reactors.
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).
Abridged History of Reactor and Fuel Cycle Technologies Development: A White Paper for the Reactor and Fuel Cycle Technology Subcommittee of the Blue Ribbon Commission
Abridged History of Reactor and Fuel Cycle Technologies Development: A White Paper for the Reactor and Fuel Cycle Technology Subcommittee of the Blue Ribbon Commission
The almost limitless energy of the atom was first harnessed in the United States, as scientists proved the basic physics of nuclear fission in a rudimentary reactor built in the floor of a squash court at the University of Chicago in 1942, and then harnessed that proven energy source in the form of atomic weapons used to end World War II. Scientists who accomplished this feat moved quickly after World War II to harness that power for peaceful uses, focusing primarily on electricity generation for industry, commerce, and household use.
U.S. Department of Energy Nuclear Waste Fund Fee Adequacy Assessment Report
U.S. Department of Energy Nuclear Waste Fund Fee Adequacy Assessment Report
The purpose of this U.S. Department of Energy Nuclear Waste Fund Fee Adequacy Assessment
Report (Assessment) is to present an analysis of the adequacy of the fee being paid by nuclear
power utilities for the permanent disposal of their SNF and HLW by the United States
government.
This Assessment consists of six sections: Section 1 provides historical context and a comparison
to previous fee adequacy assessments; Section 2 describes the system, cost, income, and
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:
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.
CURRENT U.S. DEPARTMENT OF ENERGY NUCLEAR ENERGY RD&D PROGRAMS AND PLANS
CURRENT U.S. DEPARTMENT OF ENERGY NUCLEAR ENERGY RD&D PROGRAMS AND PLANS
This document summarizes DOE’s commercial nuclear energy RD&D program based on a R&D roadmap and on DOE/NE’s budget request for fiscal year 2011. The roadmap is written at a high level and is mostly qualitative in terms of activities, milestones and decisions to be made and does not contain budget information. The fiscal year 2011 budget request contains more specific and detailed information on activities, milestones, decisions, and budgets but only for fiscal year 2011 and the two preceding fiscal years.
Review of DOE's Nuclear Energy Research and Development Program - Summary
Review of DOE's Nuclear Energy Research and Development Program - Summary
There has been a substantial resurgence of interest in nuclear power in the United States
over the past few years. One consequence has been a rapid growth in the research
budget of DOE’s Office of Nuclear Energy (NE). In light of this growth, the Office of
Management and Budget included within the FY2006 budget request a study by the
National Academy of Sciences to review the NE research programs and recommend
priorities among those programs. The programs to be evaluated were: Nuclear Power
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.
Nuclear Energy Research and Development Roadmap
Nuclear Energy Research and Development Roadmap
To achieve energy security and greenhouse gas (GHG) emission reduction objectives, the United States must develop and deploy clean, affordable, domestic energy sources as quickly as possible. Nuclear power will continue to be a key component of a portfolio of technologies that meets our energy goals. This document provides a roadmap for the Department of Energy’s (DOE’s) Office of Nuclear Energy (NE) research, development, and demonstration activities that will ensure nuclear energy remains viable energy option for the United States.
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).
RETHINKING THE CHALLENGE OF HIGH-LEVEL NUCLEAR WASTE: Strategic Planning for Defense High-Level Waste and Spent Fuel Disposal
RETHINKING THE CHALLENGE OF HIGH-LEVEL NUCLEAR WASTE: Strategic Planning for Defense High-Level Waste and Spent Fuel Disposal
An Historical and Prospective View of Romanian Decision Making in the Nuclear Domain
An Historical and Prospective View of Romanian Decision Making in the Nuclear Domain
The following graphics were developed by NF Marin Constantin (INR) for presentation and discussion at the 2nd NSG meeting in Romania (January 2008). 1. DMP for LILW Repository in Romania - Main Phases 2. Romanian History of Nuclear Power - Main Facts and Decisions 3. Cernavoda Area DMP: Dialogue Planning Including CIP Actions 4. Hypothetical Nuclear Industry Formulation of the DMP Stakes and Issues 5. Hypothetical Public Formulation of the DMP Stakes and Issues 6. How to Improve the Public Contribution to the DMP? Proposal for NSG Discussion