Category of Content
Siting Experience Documents Only
Publication Date
Subject Matter
Country
Keywords
Learning More Together Annual Report 2011
Learning More Together Annual Report 2011
Choosing a Way Forward The Future Management of Canada’s Used Nuclear Fuel (Final Study)
Choosing a Way Forward The Future Management of Canada’s Used Nuclear Fuel (Final Study)
Suspension of Expressions of Interest
Suspension of Expressions of Interest
Understanding the Choices The Future Management of Canada’s Used Nuclear Fuel
Understanding the Choices The Future Management of Canada’s Used Nuclear Fuel
Understanding the Choices is the NWMO’s second discussion document, an important milestone in a three-year study (2002-2005) designed to recommend to the Government of Canada an approach to managing Canada’s used nuclear fuel for the long term. The report begins with an examination of the values and priorities of Canadians, and how the NWMO has used this understanding to build a framework to assess and compare management approaches.
INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - English River First Nation, Saskatchewan
INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - English River First Nation, Saskatchewan
On September 13, 2010, the English River First Nation expressed interest in learning more about the Nuclear Waste Management Organization (NWMO) site selection process to find an informed and willing community to host a deep geological repository for Canada’s used nuclear fuel (NWMO, 2010). This report summarizes the findings of an initial screening, conducted by Golder Associates Ltd., to evaluate the potential suitability of thirteen English River First Nation reserve areas against five screening criteria using readily available information.
SITING PROCESS FOR A CENTRALISED STORAGE FACILITY (ATC) FOR SPENT FUEL AND HIGH LEVEL WASTE IN SPAIN
SITING PROCESS FOR A CENTRALISED STORAGE FACILITY (ATC) FOR SPENT FUEL AND HIGH LEVEL WASTE IN SPAIN
Response of the UK Government and the Department of the Environment, Northern Ireland to the Committee on Radioactive Waste management (CoRWM) Report on 'Geological Disposal of Higher Activity Radioactive Wastes'
Response of the UK Government and the Department of the Environment, Northern Ireland to the Committee on Radioactive Waste management (CoRWM) Report on 'Geological Disposal of Higher Activity Radioactive Wastes'
The primary task of the Committee on Radioactive Waste Management (CoRWM) is to provide independent scrutiny of the Government’s and Nuclear Decommissioning Authority’s proposal, plans and programmes to deliver geological disposal, together with robust interim storage, as the long-term<br/>management option for the UK’s higher activity wastes. In June 2007 the Scottish Executive announced a policy of near-surface, near-site long-term storage rather than geological disposal.
Selecting the Site: The Final Disposal at Olkiluoto
Selecting the Site: The Final Disposal at Olkiluoto
Posiva webpage discussing selecting the site for final disposal of spent fuel.
Nuclear Waste Management in Finland
Nuclear Waste Management in Finland
A summary of nuclear waste management in Finland, including energy use statistics, principles of nuclear waste management, financing, how waste is disposed of, the underground research laboratory, and the authorities involved in nuclear waste management.
Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites
Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites
This report discusses the status of the commercial spent nuclear fuel (SNF) inventory in the United States, at both decommissioned and operating commercial nuclear power reactor sites; summarizes the contractual arrangement the government and utilities have under the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (10 CFR Part 961) (Standard Contract), related litigation, and the financial liabilities resulting from the Department’s delay in performance under these contracts; provides a history of interim storage policy as it relates to commercial SN
Advanced Fuel Cycle Cost Basis
Advanced Fuel Cycle Cost Basis
This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models.
From Integral Experiments to Nuclear Data Improvement
From Integral Experiments to Nuclear Data Improvement
Target accuracy on LWR neutronics parameters is 2 to 5 times lower than the a priori uncertainty (1σ)
due to nuclear data. This paper summarizes the experimental facilities and the integral measurements that are required
for code qualification. The rigorous use of integral information through trend analysis method is described. Trends
on JEF2 data from Keff measurements and P.I.Es are presented. These trends were accounted for in the new JEFF3
evaluations. The role of fundamental experiments, such as worth measurement of separated isotopes, is emphasized.
Criticality Evaluation of Degraded Internal Configurations for the PWR AUCF WP Designs
Criticality Evaluation of Degraded Internal Configurations for the PWR AUCF WP Designs
The purpose of this analysis is to provide input on the criticality potential of various degraded configurations to an analysis on the probability of a criticality event in a Pressurized Water Reactor (PWR) Advanced Uncanistered Fuel (AUCF) Waste Package (WP).
Spent Nuclear Fuel: Accumulating Quantities at Commercial Reactors Present Storage and Other Challenges
Spent Nuclear Fuel: Accumulating Quantities at Commercial Reactors Present Storage and Other Challenges
The amount of spent fuel stored on-site at commercial nuclear reactors will continue to accumulate—increasing by about 2,000 metric tons per year and likely more than doubling to about 140,000 metric tons—before it can be moved off-site, because storage or disposal facilities may take decades to develop. In examining centralized storage or permanent disposal options, GAO found that new facilities may take from 15 to 40 years before they are ready to begin accepting spent fuel. Once an off-site facility is available, it will take several more decades to ship spent fuel to that facility.
SCALE-4 Analysis of Pressurized Water REactor Critical Configurations: Volume 5 - North Anna Unit 1 Cycle 5
SCALE-4 Analysis of Pressurized Water REactor Critical Configurations: Volume 5 - North Anna Unit 1 Cycle 5
The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor
(AFR) criticality safety analyses be validated against experimental measurements. If credit for the
negative reactivity of the depleted (or spent) fuel isotopics is desired, it is necessary to benchmark
computational methods against spent fuel critical configurations. This report summarizes a portion
of the ongoing effort to benchmark AFR criticality analysis methods using selected critical
configurations from commercial pressurized-water reactors (PWR).
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
This paper presents an evaluation of the amount of burnup credit needed for high-density casks to
transport the current U.S. inventory of commercial spent nuclear fuel (SNF) assemblies. A prototypic
32-assembly cask and the current regulatory guidance were used as bases for this evaluation.
By comparing actual pressurized-water-reactor (PWR) discharge data (i.e., fuel burnup and initial
enrichment specifications for fuel assemblies discharged from U.S. PWRs) with actinide-only-based
PWR Axial Burnup Profile Analysis
PWR Axial Burnup Profile Analysis
Monitored Retrievable Storage Project Plan
Monitored Retrievable Storage Project Plan
The purpose of this document is to describe the Monitored Retrievable Storage (MRS) Project and to establish approved cost and schedule baselines against which overall progress and management effectiveness shall be measured. For the sake of brevity, this Project Plan will be referred to as the Plan throughout this document.
Fast Flux Test Facility (FFTF) Reactor Fuel Criticality Calculations
Fast Flux Test Facility (FFTF) Reactor Fuel Criticality Calculations
The purpose of these calculations is to characterize the criticality safety concerns for the storage of Fast Flux Test Facility (FFTF) nuclear fuel in a Department of Energy spent nuclear fuel (DOE SNF) canister in a co-disposal waste package. These results will be used to support the analysis that will be done to demonstrate concept viability related to use in the Monitored Geologic Repository (MGR) environment.
DHLW Glass Waste Package Criticality Analysis (SCPB: N/A)
DHLW Glass Waste Package Criticality Analysis (SCPB: N/A)
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to determine the viability of the Defense High-Level Waste (DHLW) Glass waste package concept with respect to criticality regulatory requirements in compliance with the goals of the Waste Package Implementation Plan (Ref. 5.1) for conceptual design. These design calculations are performed in sufficient detail to provide a comprehensive comparison base with other design alternatives.
FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES
FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES
Criticality Evaluation of Degraded Internal Configurations for a 44 BWR Waste Package
Criticality Evaluation of Degraded Internal Configurations for a 44 BWR Waste Package
The purpose of this calculation is to perform an example criticality evaluation for degraded internal configurations of a boiling water reactor (BWR) waste package (WP) containing 44 spent nuclear fuel (SNF) assemblies.
EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages
EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages
The Monitored Geologic Repository (MGR) Waste Package Operations (WPO) of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Shippingport Pressurized Water Reactor (PWR) (Ref. 1). The Shippingport PWR SNF has been considered for disposal at the proposed Yucca Mountain site.
Isotopic Generation and Confirmation of the BWR Appl. Model
Isotopic Generation and Confirmation of the BWR Appl. Model
The objective of this calculation is to establish an isotopic database to represent commercial spent nuclear fuel (CSNF) from boiling water reactors (BWRs) in criticality analyses performed for the proposed Monitored Geologic Repository at Yucca Mountain, Nevada. Confirmation of the conservatism with respect to criticality in the isotopic concentration values represented by this isotopic database is performed as described in Section 3.5.3.1.2 of the Disposal Criticality Analysis Methodology Topical Report (Reference 7.1).