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Insights on Conducting Consent-Based Siting of Radioactive Waste Management Facilities: Evidence from a Nationwide Survey of US Residents

Insights on Conducting Consent-Based Siting of Radioactive Waste Management Facilities: Evidence from a Nationwide Survey of US Residents

Author(s)
Hank C. Jenkins-Smith ,
Kuhika Gupta ,
Carol L. Silva ,
Kerry G. Herron ,
Joseph T. Ripberger ,
Matthew Nowlin ,
Rob P. Rechard
Publication Date
Abstract does not exist for this document.

Public Preferences Related to Consent-Based Siting of Radioactive Waste Management Facilities for Storage and Disposal: Analyzing Variations over Time, Events, and Program Designs

Public Preferences Related to Consent-Based Siting of Radioactive Waste Management Facilities for Storage and Disposal: Analyzing Variations over Time, Events, and Program Designs

Author(s)
Hank C. Jenkins-Smith ,
Carol L. Silva ,
Kerry G. Herron ,
Kuhika G. Ripberger ,
Matthew Nowlin ,
Joseph Ripberger ,
Evaristo “Tito” Bonano ,
Rob P. Rechard
Publication Date
Abstract does not exist for this document.

Views and Attitudes toward Nuclear Waste: National Survey Final Report

Views and Attitudes toward Nuclear Waste: National Survey Final Report

Author(s)
Ipsos Reid Public Affairs
Publication Date

In 2002, the federal government passed a law to create the Nuclear Waste Management Organization, also known by its initials NWMO. The Nuclear Waste Management Organization (NWMO) was established by Ontario Power Generation Inc., Hydro-Québec and New Brunswick Power Corporation in accordance with the Nuclear Fuel Waste Act (NFWA) to assume responsibility for the long-term management of Canada’s used nuclear fuel. More specifically, the NWMO’s initial objective was to recommend a long-term approach for managing used nuclear fuel produced by Canada’s electricity generators.

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

WHF and RF Thermal Evaluation

WHF and RF Thermal Evaluation

Author(s)
Bechtel SAIC Company, LLC
Publication Date
The purpose of this analysis is to estimate the peak fuel assembly cladding temperature within the transportation casks that will be received in the WHF and RF, and to compare this value with established temperature limits. Thermally limiting scenarios are evaluated for both normal and off-normal operating conditions, with the off-normal condition defined as a loss of active ventilation. A second purpose of this analysis is to identify a specific room in the surface facilities as thermally limiting of all the rooms, with respect to the potentially highest temperatures on the concrete walls.
thermal analysis transportation yucca mountain heat load

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.
yucca mountain criticality analysis mox fuel pwr snf

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 low-enriched uranium monitored geologic repository storage mox fuel waste package degradation pwr snf corrosion plutonium oxide geochemical analysis bba000000-01717-0210-00009 uranium oxide

Data Qualification Report: Mineralogy Data for Use on the Yucca Mountain Project

Data Qualification Report: Mineralogy Data for Use on the Yucca Mountain Project

Author(s)
T.L. Steinborn
Publication Date
This DQR uses the technical assessment methods according to Attachment 2 of AP-SIII.2Q, Rev. 0, ICN 3, to qualify DTN LADB831321AN98.002. The data addressed in this DQR have been cited in CRWMS M&O (2000b) to support the Site Recommendation in determining the suitability of Yucca Mountain as a repository for high level nuclear waste. CRWMS M&O (2000b) refers to mineral analyses that are unqualified.
yucca mountain repository license application data qualification tdr-nbs-hs-000005 minerals xrd mineral concentration

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.
storage isotopic concentrations 21 pwr waste package waste package degradation criticality consequence bba000000-01717-0200-00057

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).
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

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

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

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

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.

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