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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 Railcar

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.
 

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.
burnup credit criticality analysis iaea-tecdoc-1547 iaea sensitivity analysis

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).
criticality pwr fuel transport cask end effect source convergence burnup axial burnup profile

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).
burnup credit transport cask storage cask criticality safety analysis
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