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A Technology Roadmap for Generation IV Nuclear Energy Systems, Ten Nations Preparing Today for Tomorrow's Energy Needs
A Technology Roadmap for Generation IV Nuclear Energy Systems, Ten Nations Preparing Today for Tomorrow's Energy Needs
The world’s population is expected to expand from
about 6 billion people to 10 billion people by the year
2050, all striving for a better quality of life. As the
Earth’s population grows, so will the demand for energy
and the benefits that it brings: improved standards of
living, better health and longer life expectancy, improved
literacy and opportunity, and many others.
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).
Issues for Effective Implementation of Burnup Credit
Issues for Effective Implementation of Burnup Credit
In the United States, burnup credit has been used in the criticality safety evaluation for storage pools at
pressurized water reactors (PWRs) and considerable work has been performed to lay the foundation for use of
burnup credit in dry storage and transport cask applications and permanent disposal applications. Many of the
technical issues related to the basic physics phenomena and parameters of importance are similar in each of these
applications. However, the nuclear fuel cycle in the United States has never been fully integrated and the
Regulatory Status of Burnup Credit for Spent-Fuel Storage and Transport Casks
Regulatory Status of Burnup Credit for Spent-Fuel Storage and Transport Casks
International Comparison of a Depletion Calculation Benchmark on Fuel Cycle Issues - Results from Phase 1 on UOx Fuels
International Comparison of a Depletion Calculation Benchmark on Fuel Cycle Issues - Results from Phase 1 on UOx Fuels
Although there are many reactor system benchmarks in the literature, they mostly
concentrate on the reactor system in isolation with only a few considering the fuel cycle.
However, there is currently increased emphasis on the performance of reactor systems
linked to their associated fuel cycle (Generation-IV for example). The published
international benchmark studies which relate to burn-up depletion calculations are
restricted to specific aspects of the fuel cycle:
Cross-Checking of the Operator Data Used for Burn Up Measurements
Cross-Checking of the Operator Data Used for Burn Up Measurements
Taking into account of the loss of reactivity of fuels at the end of their irradiation is known under the
term burnup credit (BUC). It is a question of dimensioning in a less penalizing way the devices of transport,
storage or of processing with respect to the risk of criticality. In the context of nuclear criticality safety a better
realism cannot be obtained at the price of conservatism. As a result the regulator requires measurements make it
possible to validate the adequacy between real fuels and the design assumptions. The sophistication of the
NRC Waste Confidence Rulemaking, Federal Register, 1984, 1990, 1999, and 2008
NRC Waste Confidence Rulemaking, Federal Register, 1984, 1990, 1999, and 2008
NRC Waste Confidence Rulemaking, Federal Register, 1984, 1990, 1999, and 2008
BWR Axial Profile
BWR Axial Profile
Managing the Nation's Commercial High-Level Radioactive Waste
Managing the Nation's Commercial High-Level Radioactive Waste
With the passage of the Nuclear Waste Policy Act of 1982 (NWPA), Congress for the first time established in law a comprehensive Federal policy for commercial high-level radioactive waste management, including interim storage and permanent disposal. NWPA provides sufficient authority for
developing and operating a high-level radioactive waste management system based on disposal in mined geologic repositories. Authorization
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.
Nuclear Waste: Is There a Need for Federal Interim Storage--Executive Summary--Report of the Monitored Retrievable Storage Commission
Nuclear Waste: Is There a Need for Federal Interim Storage--Executive Summary--Report of the Monitored Retrievable Storage Commission
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
Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit
Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit
This report proposes and documents a computational benchmark for the estimation of the
additional reactivity margin available in spent nuclear fuel (SNF) from fission products and minor
actinides in a burnup-credit storage/transport environment, relative to SNF compositions
containing only the major actinides. The benchmark problem/configuration is a generic burnupcredit
cask designed to hold 68 boiling water reactor (BWR) spent nuclear fuel assemblies. The
purpose of this computational benchmark is to provide a reference configuration for the
Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel
Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel
This report has been prepared to support technical discussion of and planning for future
research supporting implementation of burnup credit for boiling-water reactor (BWR) spent fuel
storage in spent fuel pools and storage and transport cask applications. The review and
discussion in this report are based on knowledge and experience gained from work performed
in the United States and other countries, including experience with burnup credit for
pressurized-water reactor (PWR) spent fuel. Relevant physics and analysis phenomena are
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,
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?
Options for Developing Public and Stakeholder Engagement for the Storage and Management of Spent Nuclear Fuel (SNF) and High Lievel Waste (HLW) in the United States
Options for Developing Public and Stakeholder Engagement for the Storage and Management of Spent Nuclear Fuel (SNF) and High Lievel Waste (HLW) in the United States
This report puts forth a number of options and recommendations for how to engage
stakeholders and other members of the public in the storage and management of spent
nuclear fuel and high level waste in the United States. The options are generated from a
scientific review of existing publications proposing criteria for assessing past efforts to
engage publics and stakeholders in decision-making about risky technologies. A set of
nine principles are derived for evaluating cases of public and stakeholder engagement with
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
Utilization of the EPRI Depletion Benchmarks for Burnup Credit Validation
Utilization of the EPRI Depletion Benchmarks for Burnup Credit Validation
Pressurized water reactor (PWR) burnup credit validation is
demonstrated using the benchmarks for quantifying fuel reactivity
decrements, published as Benchmarks for Quantifying Fuel Reactivity
Depletion Uncertainty, Electric Power Research Institute (EPRI)
report 1022909. This demonstration uses the depletion module
TRITON (Transport Rigor Implemented with Time-Dependent
Operation for Neutronic Depletion) available in the SCALE 6.1
(Standardized Computer Analyses for Licensing Evaluations) code
Feasibility of Direct Disposal of Dual-Purpose Canisters-Options for Assuring Criticality Control
Feasibility of Direct Disposal of Dual-Purpose Canisters-Options for Assuring Criticality Control
The concept of direct disposal of dual-purpose canisters (DPCs) has not been previously considered
for the Yucca Mountain geologic repository because of concerns, among other reasons,
about degradation of the reactivity-control material over the relatively long period of the repository
analyses. Aluminum-based neutron absorber materials, typically used in DPCs, are not
expected to have sufficient corrosion resistance necessary to retain their integrity over a 10,000+
Japan's Spent Fuel and Plutonium Management Challenges
Japan's Spent Fuel and Plutonium Management Challenges
Japan’s spent fuel management and fuel cycle programs are now at a critical stage. Its first commercial-scale reprocessing plant, at Rokkasho Village, will soon start full-scale operation.
Disposal and Storage of Spent Nuclear Fuel--Finding the Right Balance--A Report to Congress and the Secretary of Energy
Disposal and Storage of Spent Nuclear Fuel--Finding the Right Balance--A Report to Congress and the Secretary of Energy
The Nuclear Waste Policy Act of 1982, as amended, established a statutory basis
for managing the nation’s civilian (or commercially produced) spent nuclear
fuel. The law established a process for siting, developing, licensing, and constructing
an underground repository for the permanent disposal of that waste.
Utilities were given the primary responsibility for storing spent fuel until it is
accepted by the Department of Energy (DOE) for disposal at a repository —
originally expected to begin operating in 1998. Since then, however, the repository
Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages
Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay.
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
This paper provides insights into the neutronic similarities between a representative high-capacity rail-transport cask containing typical pressurized water reactor (PWR) spent nuclear fuel assemblies and critical reactor state-points, referred to as commercial reactor critical (CRC) state-points. Forty CRC state-points from five PWRs were analyzed, and the characteristics of CRC state-points that may be applicable for validation of burnup-credit criticality safety calculations for spent fuel transport/storage/disposal systems were identified.