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Identification of Sites within the Palo Duro Basin: Volume 3--Responses to Comments
Identification of Sites within the Palo Duro Basin: Volume 3--Responses to Comments
This document responds to comments received by the U.S. Department<br/>of Energy (DOE) on the draft report entitled Identification of Sites Within the Palo Duro Basin: Volume I--Palo Duro Location A (in Deaf Smith County) and Volume II--Palo Duro Location B (in Swisher County), BMI/ONWI-531, February, 1984.
Sensitivity Coefficient Generation for a Burnup Credit Cask Model Using TSUNAMI-3D
Sensitivity Coefficient Generation for a Burnup Credit Cask Model Using TSUNAMI-3D
Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs
Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs
Current Status and Potential Benefits of Burnup Credit for Spent Fuel Transportation
Current Status and Potential Benefits of Burnup Credit for Spent Fuel Transportation
PWR Burnup Credit Using Both Belts and Suspenders
PWR Burnup Credit Using Both Belts and Suspenders
Identification of Sites within the Palo Duro Basin: Volume 2--Palo Duro Location B
Identification of Sites within the Palo Duro Basin: Volume 2--Palo Duro Location B
This three-volume document narrows to two sites for continued investigations for potential nuclear waste repository sites in the Palo Duro Basin of the Texas Panhandle. Volume 1 narrows a site previously identified in Deaf Smith County, Texas; Volume 2 narrows a site previously identified in Swisher County, Texas; and Volume 3 contains responses to comments received regarding the drafts of Volumes 1 and 2 (BMI/ONWI-531).<br/>These volumes discuss the methodology and logic used as well as the results that narrowed these sites.
Joint Convention Answers on Questions to Hungary in 2009
Joint Convention Answers on Questions to Hungary in 2009
Joint Convention Answers on Questions to Hungary in 2009
Joint Convention Questions Posted to Hungary 2006
Joint Convention Questions Posted to Hungary 2006
Joint Convention Questions Posted to Hungary in 2006
Illuminating the Decision Path: The Yucca Mountain Site Recommendation
Illuminating the Decision Path: The Yucca Mountain Site Recommendation
On February 14, 2002, U.S.
Nuclear Waste - Funds Spent to Identify a Monitored Retrievable Storage Facility Site
Nuclear Waste - Funds Spent to Identify a Monitored Retrievable Storage Facility Site
The Nuclear Waste Policy Amendments Act of 1987 established the federal<br/>Office of the Nuclear Waste Negotiator for a 5-year period. The Nuclear<br/>Waste Negotiator, appointed by the President and confirmed by the<br/>Senate, was empowered to attempt to find a state or Indian tribe willing<br/>to host a repository or a monitored retrievable storage (MB) facility for the<br/>permanent or temporary storage of nuclear waste, respectively.
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
Internationalization of the Nuclear Fuel Cycle--Goals, Strategies, and Challenges
Internationalization of the Nuclear Fuel Cycle--Goals, Strategies, and Challenges
The so-called nuclear renaissance has increased worldwide interest in nuclear power.
This potential growth also has increased, in some quarters, concern that nonproliferation
considerations are not being given sufficient attention. In particular, since the introduction of
many new power reactors will lead to requiring an increase in uranium enrichment services to
provide the reactor fuel, the proliferation risk of adding enrichment facilities in countries that do
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
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).
Regulatory Status of Burnup Credit for Spent-Fuel Storage and Transport Casks
Regulatory Status of Burnup Credit for Spent-Fuel Storage and Transport Casks
BWR Axial Profile
BWR Axial Profile
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
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
Nuclear Waste and Native America: The MRS Siting Exercise
Nuclear Waste and Native America: The MRS Siting Exercise
The U.S. government’s quest to store high-level nuclear waste has
had many interesting twists and turns. One set of developments stands
out as unique — efforts to site a temporary Monitored Retrievable
Storage (MRS) facility on lands belonging to Native Americans. We
describe the history and logic of the government’s process which led to
the involvement of Native Americans and the reactions of some tribes
to the MRS option. We also provide cross-cultural perspectives on issues