Category of Content
Siting Experience Documents Only
Publication Date
Subject Matter
Keywords
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
Alternative Means of Financing and Managing the Civilian Radioactive Waste Management Program
Alternative Means of Financing and Managing the Civilian Radioactive Waste Management Program
This report is in response to the directive of the House Appropriations Subcommittee for Energy and Water
Development that the Department of Energy (DOE) update a 1984 report of alternative means of financing and
managing (AMFM) the Office of Civilian Radioactive Waste Management (OCRWM) in the DOE. The
President’s FY 2002 budget also stated: “DOE will submit to Congress an updated report regarding alternative
approaches to finance and manage the program by June 30, 2001[.] DOE will identify in this report models of
The DOE Position on the MRS Facility
The DOE Position on the MRS Facility
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.
Description of Fracture Systems for External Criticality Reports
Description of Fracture Systems for External Criticality Reports
The purpose of this Analysis/Model Report (AMR) is to describe probabilistically the main features of the geometry of the fracture system in the vicinity of the repository. They will be used to determine the quantity of fissile material that could accumulate in the fractured rock underneath a waste package as it degrades. This AMR is to feed the geochemical calculations for external criticality reports. This AMR is done in accordance with the technical work plan (BSC (Bechtel SAIC Company) 2001 b). The scope of this AMR is restricted to the relevant parameters of the fracture system.
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).
OCRWM National Transportation Plan DOE/RW-0603 Revision 0
OCRWM National Transportation Plan DOE/RW-0603 Revision 0
This Plan outlines the Department of Energy’s (DOE) 2009 strategy and planning for developing and implementing the transportation system required to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from where the material is generated or stored to the proposed repository at Yucca Mountain, Nevada. As such, it is a historical document that reflected the DOE's thinking and/or approach in 2009.
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.
slides - Canister Confinement Integrity, Integrated Plan for Addressing Potential Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless Steel Dry Cask Storage System Canisters
slides - Canister Confinement Integrity, Integrated Plan for Addressing Potential Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless Steel Dry Cask Storage System Canisters
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
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.
Waste Acceptance System Requirements Document, Revision 5, ICN 01
Waste Acceptance System Requirements Document, Revision 5, ICN 01
The purpose of this document is to establish waste acceptance technical requirements for the U.S. Department of Energy’s (DOE) Civilian Radioactive Waste Management System (CRWMS). These requirements and functions consist of two types: (a) internal CRWMS requirements derived from the Civilian Radioactive Waste Management System Requirements Document (CRD) (DOE 2007a) as illustrated in Figure 1, and (b) acceptance criteria imposed by the CRWMS on spent nuclear fuel (SNF) and high-level waste (HLW) delivered into the CRWMS.
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''.
slides - Vision/Proposed Actions for Regulatory Improvements - Looking to the Future
slides - Vision/Proposed Actions for Regulatory Improvements - Looking to the Future
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
TEV Collision with an Emplaced 5-DHLW/DOE SNF Short Co-Disposal Waste Package
TEV Collision with an Emplaced 5-DHLW/DOE SNF Short Co-Disposal Waste Package
The objective of this calculation is to determine the structural response of the 5-DHLW/DOE (Defense High Level Waste/Department of Energy) SNF (Spent Nuclear Fuel) Short Co-disposal Waste Package (WP) when subjected (while in the horizontal orientation emplaced in the drift) to a collision by a loaded (with WP) Transport and Emplacement Vehicle (TEV) due to an over-run. The scope of this calculation is limited to reporting the calculation results in terms of maximum total stress intensities (Sis) in the outer corrosion barrier (dCB).
Report on Radioactive Waste Ownership and Management of Long-Term Liabilities in EDRAM Member Countries
Report on Radioactive Waste Ownership and Management of Long-Term Liabilities in EDRAM Member Countries
This report has been prepared by an ad-hoc Working Group (WG) formed by ANDRA (France), NUMO (Japan), NAGRA (Switzerland) and ENRESA (Spain) in May 2003, after the EDRAM meeting held in Valencia to study the situation in the different EDRAM member countries regarding the treatment of radioactive waste ownership and management of long-term liabilities.
Program of Research and Development for Management and Disposal of Commercially Generated Radioactive Wastes: Record of Decision
Program of Research and Development for Management and Disposal of Commercially Generated Radioactive Wastes: Record of Decision
This Record of Decision has been prepared pursuant to the Regulations of
the council on Environmental Quality, 40 CFR Part 1805, on the selection of a
strategy for the disposal of commercially-generated radioactive wastes and the
supporting program of research and development.
The United States Department of Energy has decided to (1) adopt a strategy to
develop mined geologic repositories for disposal of commercially-generated
high-level and transuranic radioactive wastes (while continuing to examine
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.
Radioactive Waste Repository Licensing, Synopsis of a Symposium, Executive Summary
Radioactive Waste Repository Licensing, Synopsis of a Symposium, Executive Summary
This book recounts the issues raised and the viewpoints aired at a recent symposium on
repository licensing. It summarizes the problems surrounding the setting of an
Environmental Protection Agency standard for the release of radionuclides and the
regulatory problems inherent in meeting such a standard. Symposium participants came
from a variety of federal agencies and advisory groups, state governments, public interest
groups, engineering firms, national laboratories, and foreign and international
organizations.
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.