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The BRIDGE
The BRIDGE
Viewing Back End of Nuclear Fuel Cycles Synoptically and Comparatively
Viewing Back End of Nuclear Fuel Cycles Synoptically and Comparatively
Oak Ridge Waste Management Programs: Geologic Isolation and Actinide Partitioning
Oak Ridge Waste Management Programs: Geologic Isolation and Actinide Partitioning
There are two waste management R&D programs of national significance that are being administered for ERDA by the Union Carbide Corporation — Nuclear Division (UCC/ND). The National Waste Terminal Storage (NWTS) program is concerned with the development of geologic repositories for commercial nuclear fuel cycle wastes, and is organized as the Office of Waste Isolation within UCC/ND.
National Waste Terminal Storage Program: Management and Technical Program Plan
National Waste Terminal Storage Program: Management and Technical Program Plan
This report presents a management plan and a technical program plan for the National Waste Terminal Storage (NWTS) program. It was prepared by the Office of Waste Isolation (OWI) which is part of Union Carbide Corporation-Nuclear Division (UCC-ND). These plans are based on guidance provided by the Energy Research and Development Administration (ERDA). The technical plan is an extension of over 15 years of studies of waste storage in geologic formations.
Regional Geological Assessment of the Devonian-Mississippian Shale Sequence of the Appalachian, Illinois, and Michigan Basins relative to Potential Storage/Disposal of Radioactive Wastes
Regional Geological Assessment of the Devonian-Mississippian Shale Sequence of the Appalachian, Illinois, and Michigan Basins relative to Potential Storage/Disposal of Radioactive Wastes
The thick and regionally extensive sequence of shales and associated clastic sedimentary rocks of Late Devonian and Early Mississippian age has been considered among the “nonsalt geologies” for deep subsurface containment of high-level radioactive wastes.
Spent-Fuel Test - Climax: An Evaluation of the Technical Feasibility of Geologic Storage of Spent Nuclear Fuel in Granite
Spent-Fuel Test - Climax: An Evaluation of the Technical Feasibility of Geologic Storage of Spent Nuclear Fuel in Granite
This summary volume outlines results that are covered in more detail in the final report of the Spent-Fuel Test-Climax project. The project was conducted between 1978 and 1983 in the granite Climax stock at the Nevada Test Site. Results indicate that spent fuel can be safely stored for periods of years in this host medium and that nuclear waste so emplaced can be safely retrieved. We also evaluated the effects of heat and radiation (alone and in combination) on emplacement canisters and the surrounding rock mass.
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
Part 1 - Draft - Area Recommendation Report for the Crystalline Repository Project, Volume 1
Part 1 - Draft - Area Recommendation Report for the Crystalline Repository Project, Volume 1
This Draft Area Recommendation Report for the Crystalline Repository Project identifies portions of crystalline rock bodies as proposed potentially acceptable sites for consideration in the second high-level radioactive waste repository program. <br>The U.S. Department of Energy (DOE) evaluated available geologic and environmental data for 235 crystalline rock bodies in the North Central, Northeastern, and Southeastern Regions to identify preliminary candidate areas.
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.
Appendix C - Report of the Blue Ribbon Commission on America's Nuclear Future - Report to the Secretary of Energy
Appendix C - Report of the Blue Ribbon Commission on America's Nuclear Future - Report to the Secretary of Energy
The Blue Ribbon Commission on America_s Nuclear Future (BRC) was formed by the Secretary<br>of Energy at the request of the President to conduct a comprehensive review of policies for<br>managing the back end of the nuclear fuel cycle and recommend a new strate
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).
PWR Axial Burnup Profile Analysis
PWR Axial Burnup Profile Analysis
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.
Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition-Proceedings of a Technical Meeting held in London, 29 August-2 September 2006
Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition-Proceedings of a Technical Meeting held in London, 29 August-2 September 2006
This publication records the proceedings of a technical meeting organized by the IAEA and
held in London 29 August–2 September 2005 with sixty participants from 18 countries. As
indicated in the title, the objective of this meeting was to provide a forum for exchange of
technical information on spent fuel burnup credit applications and thereby compile state-ofthe-
art information on technical advances related to spent fuel transportation, storage,
reprocessing and disposition.
Range of Neutronic Parameters Calculation File
Range of Neutronic Parameters Calculation File
The purpose of this engineering calculation is to document the benchmark range, over a variety of parameters, for the validation of the criticality calculations supporting the Monitored Geologic Repository (MGR). This engineering calculation accomplishes this by characterizing the Laboratory Critical Experiments (LCE) and the Pressurized Water Reactor (PWR) Commercial Reactor Criticals (CRC), and summarizing the significant parameters. This engineering calculation supports the Disposal Criticality Analysis Methodology program.
Operational Waste Stream Assumption for TSLCC Estimates
Operational Waste Stream Assumption for TSLCC Estimates
This document provides the background and basis for the operational waste stream used in the 2000 Total System Life Cycle Cost (TSLCC) estimate for the Civilian Radioactive Waste Management System (CRWMS). This document has been developed in accordance with its Development Plan (CRWMS M&O 2000a), and AP-3.11Q, ''Technical Reports''.
Safety Evaluation of a Geological Repository
Safety Evaluation of a Geological Repository
The Law of 30 December 1991 [1] confers to Andra the mission of assessing the feasibility of a repository of high-level and long-lived (HLLL) waste in a deep geological formation.
Burn-up Credit Criticality Safety Benchmark - Phase VII, UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal
Burn-up Credit Criticality Safety Benchmark - Phase VII, UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal
DSNF and Other Waste Form Degradation Abstraction
DSNF and Other Waste Form Degradation Abstraction
Several hundred distinct types of DOE-owned spent nuclear fuel (DSNF) may potentially be disposed in the Yucca Mountain repository. These fuel types represent many more types than can be viably individually examined for their effect on the Total System Performance Assessment for the License Application (TSPA-LA). Additionally, for most of these fuel types, there is no known direct experimental test data for the degradation and dissolution of the waste form in repository groundwaters.
Evaluation of the Technical Basis for Extended Dry Storage and Transportation of Used Nuclear Fuel – Executive Summary
Evaluation of the Technical Basis for Extended Dry Storage and Transportation of Used Nuclear Fuel – Executive Summary
The U.S. Nuclear Waste Technical Review Board (Board) is tasked by the amendments to the Nuclear Waste Policy Act of 1982 to independently evaluate U. S. Department of Energy (DOE) technical activities for managing and disposing of used nuclear fuel and high-level radioactive waste. This report was prepared to inform DOE and Congress about the current state of the technical basis for extended dry storage1 of used fuel and its transportation following storage.