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Reflecting on the Implementing Geological Disposal Technology Platform as a knowledge network and potential scenarios for stakeholder involvement
Reflecting on the Implementing Geological Disposal Technology Platform as a knowledge network and potential scenarios for stakeholder involvement
This report was prepared in the context of Work Package 3 of the InSOTEC project. The overall objective of this work package (WP) is to take a closer look at arenas where socio-technical combinations on radioactive waste management (RWM) are formed. The attempt is to illustrate the interconnections between the sources of different types of information and knowledge development with the various stakeholders having access to that information.
Underlying Yucca Mountain: The Interplay of Geology and Policy in Nuclear Waste Disposal
Underlying Yucca Mountain: The Interplay of Geology and Policy in Nuclear Waste Disposal
Nuclear waste disposal in the USA is a difficult policy issue infused with science, technology, and politics. This issue provides an example of the co-production of scientific knowledge and politics through public policy. The proponents of a repository site at Yucca Mountain, Nevada, argue that their decision to go ahead with the site is based on ‘sound science’, but the science they use to uphold their decision is influenced by politics. In turn, the politics of site selection has been altered by the scientific knowledge produced.
Regulatory History
Regulatory History
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina First National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina First National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina First National Report
Recommendation by the Secretary of Energy Regarding the Suitability of the Yucca Mountain Site for a Repository under the Nuclear Waste Policy Act of 1982
Recommendation by the Secretary of Energy Regarding the Suitability of the Yucca Mountain Site for a Repository under the Nuclear Waste Policy Act of 1982
For more than half a century, since nuclear science helped us win World War II and ring in the Atomic Age, scientists have known that the Nation would need a secure, permanent facility in which to dispose of radioactive wastes. Twenty years ago, when Congress adopted the Nuclear Waste Policy Act of 1982 (NWPA or "the Act"), it recognized the overwhelming consensus in the scientific community that the best option for such a facility would be a deep underground repository.
Nuclear Waste Policy Act (Section 112) - Environmental Assessment, Yucca Mountain Site, Nevada Research and Development Area, Nevada, Volume 1
Nuclear Waste Policy Act (Section 112) - Environmental Assessment, Yucca Mountain Site, Nevada Research and Development Area, Nevada, Volume 1
By the end of this century, the United States plans to begin operating the first geologic repository for the permanent disposal of commercial spent nuclear fuel and high-level radioactive Waste. Public Law 97-425, the Nuclear waste Policy Act of 1982 (the Act), specifies the process for selecting a repository site, and constructing, operating, closing, and decommissioning the repository.
Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canadian National Report -- Final Report
Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canadian National Report -- Final Report
This report demonstrates how Canada continues to meet its obligations under the terms of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. A collaboration by government, industry and the regulatory body, this document focuses specifically on the progress of long-term management initiatives for spent fuel and radioactive waste in Canada, revisions and updates to Canada’s Third National Report and comments and issues raised at the Third Review Meeting.
The U.S. Environmental Protection Agency’s Public Health and Safety Standards for Yucca Mountain, Nevada (40 CFR Part 197) - 9072
The U.S. Environmental Protection Agency’s Public Health and Safety Standards for Yucca Mountain, Nevada (40 CFR Part 197) - 9072
In 2001, as directed by the Energy Policy Act of 1992, the U.S. Environmental Protection Agency (EPA) issued public health and environmental radiation protection standards for the proposed repository at Yucca Mountain, Nevada. Several parties sued the Agency on a myriad of aspects of the rule. The Court ruled in EPA’s favor in all aspects of the case but one, and returned the standards to the Agency in 2004. In 2005, EPA proposed amendments to the standards. Following public hearings and a public review period, the final amendments were issued in September 2008.
Response to "Multiattribute Utility Analysis of Sites Nominated for Characterization for the First Radioactive-Waste Repository"
Response to "Multiattribute Utility Analysis of Sites Nominated for Characterization for the First Radioactive-Waste Repository"
History of Repository Regulations
History of Repository Regulations
Frequency of SNF Misload for Uncanistered Fuel Waste Package
Frequency of SNF Misload for Uncanistered Fuel Waste Package
The purpose of this engineering calculation is to estimate the frequency of misloading spent nuclear fuel (SNF) assemblies that would result in exceeding the criticality design basis of a waste package (WP). This type of misload - a reactivity misload - results from the incorrect placement of one or more fuel assemblies into a waste package such that the criticality controls do not match the required controls for the fuel assemblies. An actual criticality event can not occur in a WP unless a moderator (e.g. water) is present.
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]).
PWR Axial Burnup Profile Analysis
PWR Axial Burnup Profile Analysis
Review of the Early Site Suitability Evaluation for the proposed Yucca Mountain high-level waste repository site
Review of the Early Site Suitability Evaluation for the proposed Yucca Mountain high-level waste repository site
In response to your request, and as a follow-up to the ACNW Working Group meeting with you and your staff on June 17, 1992, we offer the following comments on the Early Site Suitability Evaluation (ESSE) for the proposed Yucca Mountain high-level waste repository site. Our comments relate both to the ESSE, as prepared by Science Applications International Corporation (SAIC), a contractor to the U.S. Department of Energy (DOE), and to the draft review prepared by your staff.
Solving the U.S. Nuclear Waste Dilemma
Solving the U.S. Nuclear Waste Dilemma
Current U.S. nuclear waste law and policy is bankrupt. The 1982 Nuclear Waste Policy Act (NWPA) set a 1998 deadline for opening a deep geologic repository to receive spent nuclear fuel (SNF) and high-level waste (HLW) from reprocessing. In 1987, Congress amended the Act to designate Yucca Mountain in Nevada as the only potential site, and severely restricted the development of any federal facility for consolidated storage of nuclear waste. Nevada’s unrelenting opposition to the Yucca repository eventually succeeded with the election of Barack Obama as President.
United States of America, Third National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
United States of America, Third National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The United States of America ratified the Joint Convention on the Safety of Spent Fuel<br/>Management and on the Safety of Radioactive Waste Management (Joint Convention) on<br/>April 9, 2003. The Joint Convention establishes an international peer review process among<br/>Contracting Parties and provides incentives for nations to take appropriate steps to bring their<br/>nuclear activities into compliance with general safety standards and practices.
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.
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).
One Step at a Time: The Staged Development of Geologic Repositories for High-Level Radioactive Waste - Summary
One Step at a Time: The Staged Development of Geologic Repositories for High-Level Radioactive Waste - Summary
A new report from the National Academies proposes a management approach called “adaptive staging” as a promising means to develop geologic repositories for high-level waste such as the proposed repository at Yucca Mountain, Nevada. Adaptive staging is a learn-as-you-go process that enables project managers to continuously reevaluate and adjust the program in response to new knowledge and stakeholder input.
Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences
Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences
Performance objectives for the geologic repository operations area through permanent closure in 10 CFR 63.111 identify compliance with regulatory dose limits for workers and members of the public as a design objective. The purpose of this design calculation is to determine direct radiation dose consequences for Category 1 and 2 event sequences. It does not include worker dose assessment for recovery operations following Category 1 event sequences.