Task Order 17 – Cask Design Study Final Report
Task Order 17 – Cask Design Study Final Report
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AREVA
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ATLAS Railcar Design Project Status Report
ATLAS Railcar Design Project Status Report
Author(s)
Matt Feldman
,
Bill Reich
Publication Date
Abstract does not exist for this document.
DOE Atlas Railcar Project End-of-Phase 2 Final Report
DOE Atlas Railcar Project End-of-Phase 2 Final Report
Author(s)
Orano Federal Services LLC
Publication Date
This is the DOE Atlas Railcar Project End-of-Phase 2 Final Report (Revision 1 from March 2018) that describes the technical progress through Phase 2 for the contract to design, analyze, and fabricate prototypes of cask and buffer railcars to transport spent nuclear fuel and high-level radioactive waste.
This is the main body of the Phase 2 final report. There are a number of appendices referenced in the main body that will be posted to CURIE at a later time.
Atlas Phase 2 Final Report Appendix A
Atlas Phase 2 Final Report Appendix A
Author(s)
Areva Federal Services LLC
Publication Date
This document provides a white paper detailing required changes to the DOE Atlas railcar conceptual cradle attachment components and Phase 1 conceptual cradle design due to the addition of the HI-STAR 190 SL and XL casks to the project.
Atlas Phase 3 Report - Prototype Fabrication and Delivery
Atlas Phase 3 Report - Prototype Fabrication and Delivery
Author(s)
Orano Federal Services LLC (Formerly Areva Federal Services, LLC)
Publication Date
The United States Department of Energy (DOE) is preparing for future large-scale transport of spent
nuclear fuel and high-level radioactive waste, which are collectively defined as High-Level Radioactive
Material (HLRM) by the Association of American Railroads (AAR). A part of this preparation includes
designing railcars to be used for the transport of HLRM.
Atlas Phase 2 Report - Preliminary Design
Atlas Phase 2 Report - Preliminary Design
Author(s)
Areva Federal Services, LLC
Publication Date
The United States Department of Energy (DOE) is preparing for future large-scale transport of spent nuclear fuel and high-level radioactive waste, which are collectively defined as High-Level Radioactive Material (HLRM) by the Association of American Railroads (AAR). A part of this preparation includes designing railcars to be used for the transport of HLRM.
Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel
Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel
Author(s)
Broadhead, B. L.
,
DeHart, M. D.
,
Ryman, J. C.
,
Tang, J. S.
,
Parks, C. V.
Publication Date
The radionuclide characteristics of light-water-reactor (LWR) spent fuel play key roles in the design
and licensing activities for radioactive waste transportation systems, interim storage facilities, and the final
repository site.
Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package
Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package
Author(s)
John A. McClure
Publication Date
The purpose of this calculation is to evaluate the transient behavior and consequences of a worstcase
criticality event involving intact pressurized water reactor (PWR) mixed-oxide (MOX)
spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR waste package
(WP). This calculation will provide information necessary for demonstrating that the
consequences of a worst-case criticality event involving intact PWR MOX SNF are insignificant
in their effect on the overall radioisotopic inventory and on the integrity of the repository.
EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages
EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages
Author(s)
Paul L. Cloke
Publication Date
The Monitored Geologic Repository (MGR) Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating (CRWMS M&O) contractor performed calculations to provide input to the design of a waste package (WP). This document analyzes the degradation processes of two types of pressurized water reactor (PWR) spent nuclear fuel (SNF):
• Fuel fabricated from low enriched uranium oxide, which has been used, or will ~ used, in commercial nuclear power plants.
Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package
Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package
Author(s)
John A. McClure
,
James R. Worsham, III
Publication Date
The purpose of this analysis is to evaluate the transient behavior and consequences of a worst case criticality event involving intact pressurized water reactor (PWR) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR assembly waste package (WP). The objective of this analysis is to demonstrate that the consequences of a worst case criticality event involving intact PWR SNF are insignificant in their effect on the overall radioisotopic inventory in a WP.
Intact and Degraded Mode Criticality Calculations for the Codisposal of ATR Spent Nuclear Fuel in a Waste Package
Intact and Degraded Mode Criticality Calculations for the Codisposal of ATR Spent Nuclear Fuel in a Waste Package
Author(s)
Dionisie R. Moscalu
Publication Date
The objective of this calculation is to perform intact and degraded mode criticality evaluations of the US Department of Energy's (DOE) Advanced Test Reactor (ATR) Spent Nuclear Fuel (SNF) placed in the DOE standardized SNF canister. This analysis evaluates the codisposal of the DOE SNF canister containing the ATR SNF in a 5-Defense High-Level Waste (%-DHLW) Short Waste Package (WP) (Bechtel SAIC Company, LLC [BSC] 2004a), which is to be placed in a monitored geologic repository (MGR).
Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation
Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation
Author(s)
Mueller, D. E.
,
Wagner, J. C.
Publication Date
The responsible use of calculational methods in nuclear criticality safety includes a
determination of bias and bias uncertainty that may exist between the calculated results and reality.
Such biases exist due to approximations used to model the real world, uncertainties in nuclear data,
and approximations associated with the calculational method (e.g., Monte Carlo method). The bias
and bias uncertainty are typically determined by using the modeling approximations, nuclear data, and
calculational method to model well-known, usually critical, systems.
OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask
OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask
Author(s)
Nouri, A.
Publication Date
The OECD/NEA “Burn-up Credit Criticality Benchmark” working group has studied the effect of
axial burn-up profile on the criticality of a realistic PWR spent fuel transport cask (Phase II-B).
The final results of this benchmark are presented and analysed in this report.
Nine basic cases and two additional accident configurations were considered with the following
varying parameters: burn-up (0 GWd/t for fresh fuel, 30 and 50 GWd/t), fuel composition (actinides
only and actinides with fifteen fission products), axial burn-up discretisation (1 or 9 zones).
Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks
Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks
Author(s)
Parks, C. V.
,
Gauld, I. C.
,
Wagner, J. C.
,
Broadhead, B. L.
,
DeHart, M. D.
,
Ebert, D. D.
Publication Date
The Nuclear Regulatory Commission (NRC) Office of Regulatory Research (RES) has initiated a program to support effective implementation of burnup credit in the criticality safety assessment of transport and dry storage casks. The goal is to develop technical bases that can be used to provide criteria and guidance for use in licensing activities.
The program is being conducted in a phased approach, with the initial focus on unresolved issues related to the use of actinide-only bumupcredit in transport and dry storage casks designed for spent fuel from pressurized-water reaciors (PWRs).
Radiolytic Specie Generation from Internal Waste Package Criticality
Radiolytic Specie Generation from Internal Waste Package Criticality
Author(s)
JOHN A. MCCLURE
,
GEORGETA RADULESCU
Publication Date
The effects of radiation on the corrosion of various metals and alloys, particularly with respect to in-reactor processes, has been discussed by a number of authors (Shoesmith and King 1998, p. 2). Shoesmith and King (1998) additionally discuss the effects of radiation on the proposed Monitored Geologic Repository (MGR) Waste Package (WP) materials. Radiation effects on the corrosion of metals and alloys include, among other things, radiolysis of the local gaseous and aqueous environment to produce both oxidizing and reducing radicals.
Intact and Degrade Mode Criticality Calculations for the Codisposal of TMI-2 Spent Nuclear Fuel in a Waste Package
Intact and Degrade Mode Criticality Calculations for the Codisposal of TMI-2 Spent Nuclear Fuel in a Waste Package
Author(s)
Lee Montierth
Publication Date
The objective of these calculations is to perform intact and degraded mode criticality evaluations of the Department of Energy’s (DOE) Three Mile Island – Unit 2 (TMI-2) spent nuclear fuel (SNF) in canisters. This analysis evaluates codisposal in a 5-Defense High-Level Waste (5-DHLW/DOE SNF) Long Waste Package (Civilian Radioactive Waste Management System Management and Operating Contractor [CRWMS M&O] 2000b, Attachment V), which is to be placed in a potential monitored geologic repository (MGR).
SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 3-Surry Unit 1 Cycle 2
SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 3-Surry Unit 1 Cycle 2
Author(s)
Hermann, O. W.
,
Bowman, S. M.
Publication Date
The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor
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.
Probabilistic External Criticality Evaluation
Probabilistic External Criticality Evaluation
Author(s)
P. Gottlieb
,
J. R. Massari
Publication Date
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to provide a probabilistic evaluation of the potential for criticality of fissile material which has been transported from a geologic repository containing breached waste packages of commercial spent nuclear fuel (SNF). This analysis is part of a continuing investigation of the probability of criticality resulting from the emplacement of spent nuclear fuel in a geologic repository.
The Likelihood of Criticality Following Disposal of SF/HLW/HEU/Pu
The Likelihood of Criticality Following Disposal of SF/HLW/HEU/Pu
Author(s)
T.W. Hicks
,
T.D. Baldwin
,
J.M. Solano
,
Galson Sciences Ltd
,
D.G. Bennett
,
TerraSalus Ltd
Publication Date
The Radioactive Waste Management Directorate (RWMD) is responsible for implementing
geological disposal of the UK’s higher-activity radioactive wastes. RWMD’s research into
geological disposal considers safety during waste transport to a disposal facility, during
waste disposal operations, and once the facility has been closed. The wastes for disposal
comprise a wide range of materials and include some fissile radionuclides.
Supplement to the Disposal Criticality Analysis Methodology
Supplement to the Disposal Criticality Analysis Methodology
Author(s)
CRWMS
Publication Date
The Disposal Criticality Analysis Methodology Topical Report, YMP/TR-0004Q (DOE 1998b) described a risk-informed methodology for postclosure criticality analyses in the potential repository at Yucca Mountain, Nevada. Various models contained in the methodology were described and a process for validating these models was presented. The topical report also committed to following this process in validating the models used for License Application.
Screening Analysis of Criticality Features, Events, and Processes for License Application
Screening Analysis of Criticality Features, Events, and Processes for License Application
Author(s)
Sandia National Laboratories
Publication Date
The purpose of this analysis report is to evaluate the features, events, and processes (FEPs) associated with criticality and document the screening decision for either inclusion or exclusion of criticality in the Total System Performance Assessment for License Application (TSPA-LA). The FEPs associated with criticality address scenarios that include initiators of sequences of events or processes that could lead to configurations that have potential for criticality in the repository.
Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel: 2022 Update
Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel: 2022 Update
Author(s)
U.S. Nuclear Waste Technical Review Board
Publication Date
In October 2009, the U.S. Nuclear Waste Technical Review Board (Board or NWTRB) published Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel. For each of the 13 national programs studied, the report catalogued 15 institutional arrangements that had been set in place and 15 technical approaches that had been taken to design repository systems for the long-term management of high-activity radioactive waste.
Disposition of High-Level Waste and Spent Nuclear Fuel: The Continuing Societal and Technical Challenges
Disposition of High-Level Waste and Spent Nuclear Fuel: The Continuing Societal and Technical Challenges
Author(s)
National Research Council
Publication Date
There has been, for decades, a worldwide consensus in the nuclear technical community for disposal through geological isolation of high-level waste (HLW), including spent nuclear fuel (SNF). However, none of the national programs established to implement geological disposal has yet succeeded in establishing a geological repository and emplacing HLW in it. The large and growing HLW inventory from civilian and military reactor use over nearly 60 years remains in surface facilities intended only for interim storage.
