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

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.
burnup credit scale pwr ornl/tm-12294/v3 surry

Science based responses to social myths on nuclear energy

Science based responses to social myths on nuclear energy

Author(s)
Robert Hayes
Publication Date

In order to promote a sound basis for considering the role of nuclear in climate change, this review spans the technical topics of social and political debate surrounding nuclear energy with a focus on the objective science of these issues including nuclear waste, accidents and overall risk. Novel aspects include the emergence of nuclear energy as being potentially renewable and the antithesis of Fukushima being an argument for the unacceptable risks associated with the use of nuclear energy.

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.
criticality safety mined geologic repository external criticality breached waste package

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.
disposal criticality criticality safety heu used fuel disposition hlw geologic disposal facility gdf sf rwmd/003/001 17293-tr-022

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

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.
criticality yucca mountain criticality analysis license application nrc storage regulations postclosure

Why DOE's Messages on Transportation Don't Resonate with the Public (and What DOE Can Do to Fix the Problem)

Why DOE's Messages on Transportation Don't Resonate with the Public (and What DOE Can Do to Fix the Problem)

Author(s)
Lisa R. Janairo ,
Ken Niles
Publication Date
This paper describes the U.S. Department of Energy’s (DOE) challenge in addressing public perceptions about the planned transport of spent nuclear fuel and high-level nuclear waste to a national repository. The authors focus on ways to improve one small but important component of a well-designed effort to manage social risk – namely, public outreach. After reviewing fundamental principles of risk perception, the authors examine DOE’s own public information materials from various radioactive waste shipping campaigns to determine the extent to which DOE uses such messages.
communication public outreach information

FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES

FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES

Author(s)
Van Ness Feldman
Publication Date
At the request of the Blue Ribbon Commission Staff,1 Van Ness Feldman examined the following question: What commitments has the Federal Government made to states, communities, private companies, and others related to the disposal of used fuel and high-level wastes? Spent nuclear fuel (referred to herein as “used fuel”) and high-level radioactive waste (“HLW”) are the by-products of commercial nuclear energy generation, defense production of nuclear weapons materials, and research and medical activities that utilize nuclear reactors or fission product nuclides. This paper describes the Federal
transportation high level waste spent fuel government blue ribbon commission legal analysis used fuel responsibility

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.

UNF-STANDARDS presentation to EPRI extended storage collaboration project

UNF-STANDARDS presentation to EPRI extended storage collaboration project

Author(s)
John Scaglione
Publication Date

Understanding the changing nuclear and mechanical characteristics of used nuclear fuel (UNF) over time and how these changing characteristics affect storage, transportation, and disposal options can require many tools and types of data. To streamline analysis capabilities for the waste management system, a comprehensive, integrated data and analysis tool has been assembled—UNF-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS).

disposal transportation data storage database used nuclear fuel

Presentation made at IAEA on A Unified Spent Nuclear Fuel (SNF) Database and Analysis System

Presentation made at IAEA on A Unified Spent Nuclear Fuel (SNF) Database and Analysis System

Author(s)
Scaglione
Publication Date

Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.

iaea snf unified database

Sister Rod Examinations at ORNL for the HBU Spent Fuel Data Project

Sister Rod Examinations at ORNL for the HBU Spent Fuel Data Project

Author(s)
Montgomery ,
Scaglione ,
Bevard
Publication Date

Presentation made at the Electric Power Research Institute (EPRI) Extended Storage Collaboration Project (ESCP) meeting November 2016 discussing the status of nondestructive examinations being performed on high burnup (HBU) sent nuclear fuel (SNF) rods at Oak Ridge National Laboratory and proposed destructive examinations that will be performed over the next several years.

testing spent fuel high burnup

Hosting a Nuclear Facility: Mayors Discuss Role of Community Engagement

Hosting a Nuclear Facility: Mayors Discuss Role of Community Engagement

Author(s)
Irena Chatzis, IAEA Department of Nuclear Energy
Publication Date

Engaging local stakeholders through transparent and open dialogue is pivotal for the success of nuclear projects. Engagement requires time, trust-building and adaptability as expectations evolve. In many places, communities that initially expressed scepticism or opposition have become advocates because of this engagement and better understanding of what it means to host a nuclear facility.

A Community Handbook on Nuclear Energy

A Community Handbook on Nuclear Energy

Author(s)
Colton, Kara ,
Doman, Allison ,
Kirshenberg, Seth
Publication Date

This handbook was prepared by Energy Communities Alliance (ECA) with funding from the U.S. Department of Energy (DOE), Office of Nuclear Energy, under Cooperative Agreement DE-NE0000006. It does not represent the views of the Department of Energy, and no official endorsement should be inferred. This handbook is an update to the version originally released in March 2012. The authors are Kara Colton, Allison Doman and Seth Kirshenberg of ECA.

CSNF Loading Curve Sensitivity Analysis

CSNF Loading Curve Sensitivity Analysis

Author(s)
Sandia National Laboratories
Publication Date

The purpose of this scientific analysis report, CSNF Loading Curve Sensitivity Analysis, is to establish the required minimum burnup as a function of initial enrichment for both pressurized water reactor (PWR) and boiling water reactor (BWR) commercial spent nuclear fuel (CSNF) that would allow permanent disposal of these waste forms in the geologic repository at Yucca Mountain. The relationship between the required minimum burnup and fuel assembly initial enrichment forms a loading curve.

burnup credit transportation, aging and disposal (tad) yucca mountain commercial spent nuclear fuel criticality analysis repository loading curves

DOE SNF Phase I and II Summary Report

DOE SNF Phase I and II Summary Report

Author(s)
Bechtel SAIC Company, LLC
Publication Date

There are more than 250 forms of U.S. Department of Energy (DOE)­owned spent nuclear fuel (SNF). Due to the variety of the spent nuclear fuel, the National Spent Nuclear Fuel Program (NSNFP) has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. For each fuel group, a fuel type that represents the characteristics of all fuels in that group has been selected for detailed analysis.

high level waste criticality analysis repository waste acceptance doe spent nuclear fuel defense

Initial Radionuclide Inventories

Initial Radionuclide Inventories

Author(s)
Bechtel SAIC Company, LLC
Publication Date

The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only.

yucca mountain commercial spent nuclear fuel license application radionuclides postclosure co-disposal waste package isotopic concentrations

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Author(s)
Spent Fuel Project Office, NRC

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1

burnup credit pwr spent fuel transport cask storage cask criticality safety analysis isg-8 interim staff guidance used fuel

OECD/NEA Burnup Credit Criticality Benchmarks Phase IIIB: Burnup Calculations of BWR Fuel Assemblies for Storage and Transport

OECD/NEA Burnup Credit Criticality Benchmarks Phase IIIB: Burnup Calculations of BWR Fuel Assemblies for Storage and Transport

Author(s)
Okuno, Hiroshi ,
Naito, Yoshitaka ,
Suyama, Kenya
Publication Date

The report describes the final results of the Phase IIIB Benchmark conducted by the
Expert Group on Burnup Credit Criticality Safety under the auspices of the Nuclear Energy
Agency (NEA) of the Organization for Economic Cooperation and Development (OECD).
The Benchmark was intended to compare the predictability of current computer code and
data library combinations for the atomic number densities of an irradiated BWR fuel
assembly model. The fuel assembly was irradiated under specific power of 25.6 MW/tHM

burnup credit criticality analysis nea jaeri nea/nsc/doc(2002)/2 composition calculations
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