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General Reports, Various Sources, NUREGs, etc

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

March 1, 1995

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.

General Reports, Various Sources, NUREGs, etc

Supplement to the Disposal Criticality Analysis Methodology

Author(s)

CRWMS

Publication Date

September 1, 1999

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.

disposal neutronics analysis yucca mountain criticality analysis repository license application storage postclosure risk models b00000000-01717-5705-00137

General Reports, Various Sources, NUREGs, etc

Screening Analysis of Criticality Features, Events, and Processes for License Application

Author(s)

Sandia National Laboratories

Publication Date

February 1, 2008

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.

criticality yucca mountain criticality analysis license application nrc storage regulations postclosure

Program Documents

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

October 1, 2004

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).

criticality yucca mountain advanced test reactor monitored geologic repository co-disposal waste package doe spent nuclear fuel 5 dhlw wp waste package degradation spent fuel degradation atr spent nuclear fuel neutron multiplication factor cal-dsd-nu-000007

Program Documents

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

June 1, 1995

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.

burnup credit spent fuel transport lwr ornl/tm-12742 nuclide used fuel

Software/Models

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

March 1, 2004

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).

spent fuel criticality safety three mile island degraded assemblies codisposal waste package used fuel

Nuclear Power Plant Infrastructure Evaluations for Removal of Spent Nuclear Fuel (2024)

Author(s)

SJ Maheras ,

LS Rodman ,

VO Peoples ,

AH Levin ,

VM Wilson ,

D Carpenter-Graffy ,

RE Best ,

J Moore ,

K Langan

Publication Date

February 29, 2024

This report fulfills the M3 milestone M3SF-23PN0203020614, “Updated NPP Site Evaluation Report (2).” This report is an update of the 2021 report Nuclear Power Plant Infrastructure Evaluations for Removal of Spent Nuclear Fuel and includes expansion of the site evaluations to include operating nuclear power plant (NPP) sites and to incorporate updated site inventory data. Figures that include the number of spent nuclear fuel (SNF) assemblies and metric tons heavy metal (MTHM) in a single figure have also been added to the report.

Atlas Railcar factsheet

Author(s)

DOE Office of Nuclear Energy

Publication Date

October 1, 2020

The U.S. Department of Energy (DOE) is developing special railcars for future large-scale DOE transport of spent nuclear fuel (SNF) from nuclear power plants. Designs include new buffer railcars, the Atlas railcar (to transport SNF containers), and a new escort railcar for security personnel that was developed in collaboration with the U.S. Navy. All railcars are expected to complete testing and meet North American freight safety standards in 2023.

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

July 1, 2022

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.

General Reports, Various Sources, NUREGs, etc

DOE Atlas Railcar Project End-of-Phase 2 Final Report

Author(s)

Orano Federal Services LLC

Publication Date

March 1, 2018

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 I Report

Author(s)

Areva Federal Services, LLC

Publication Date

October 28, 2016

In preparation of an integrated nuclear waste management program, the United States
Department of Energy (DOE) is preparing for future large-scale transport of spent nuclear fuel
(SNF), high-level radioactive waste (HLW), and Greater-Than-Class-C (GTCC) waste. A part of
this preparation includes developing a fleet of railcars to be used for the transport of High-Level
Radioactive Material (HLRM) and GTCC waste.

Atlas Phase 2 Report - Preliminary Design

Author(s)

Areva Federal Services, LLC

Publication Date

March 6, 2018

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 3 Report - Prototype Fabrication and Delivery

Author(s)

Orano Federal Services LLC (Formerly Areva Federal Services, LLC)

Publication Date

May 13, 2019

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 Final Report Appendix A

Author(s)

Areva Federal Services LLC

Publication Date

February 2, 2018

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.