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Development and Applications of a Protypic SCALE Control Module for Automated Burnup Credit Analysis
Development and Applications of a Protypic SCALE Control Module for Automated Burnup Credit Analysis
Use Burnup Credit for Criticality Safety for the Hanford Spent Nuclear Fuel Project
Use Burnup Credit for Criticality Safety for the Hanford Spent Nuclear Fuel Project
Impact of Partially Inserted Control Rods on Actinide-Only Burnup Credit Margin
Impact of Partially Inserted Control Rods on Actinide-Only Burnup Credit Margin
A New Method to Take Burnup into Account in Criticality Studies Considering an Axial Profile of Burn-up Plus some Fission Products
A New Method to Take Burnup into Account in Criticality Studies Considering an Axial Profile of Burn-up Plus some Fission Products
Initial Site-Specific De-Inventory Reports
Initial Site-Specific De-Inventory Reports
The US Department of Energy (DOE) is exploring options for developing a large-scale transportation system for the safe transport of spent nuclear fuel (SNF) and high-level radioactive waste to future storage or disposal facilities. This complex, large-scale transportation system will involve coordinated, integrated activities. Interfaces with various transportation and non-transportation activities must be defined, and systems must be developed to ensure successful integration when the system becomes operational.
Consent-Based Siting Roadmap
Consent-Based Siting Roadmap
The U.S. Department of Energy is pursuing one or more federal consolidated interim storage facilities to store the nation's commercial spent nuclear fuel in the near-term using a multistage consent-based approach that puts communities' interest at the forefront.
Consent-Based Siting Consortia Awardee Branding Assets
Consent-Based Siting Consortia Awardee Branding Assets
The attached files provide logo image files and guidance about how to properly use the Awardee brand and logo that should be included with any presentations and material developed by awardees.
Nuclear Power Plant Infrastructure Evaluations for Removal of Spent Nuclear Fuel (2024)
Nuclear Power Plant Infrastructure Evaluations for Removal of Spent Nuclear Fuel (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.
Let the Talk Count: Attributes of Stakeholder Engagement, Trust, Perceive Environmental Protection and CSR
Let the Talk Count: Attributes of Stakeholder Engagement, Trust, Perceive Environmental Protection and CSR
This article tests the links between attributes of stakeholder engagement (information sharing [quantity and quality of information sharing], procedural fairness [respectful treatment and providing voice], and empathy) and local communities’ acceptance of corporate social responsibility (CSR) initiatives with the mediating roles of trust and perceived environmental protection. Using Ghana as a case, survey data were collected from 604 local inhabitants in mining communities for the study.
Spent Nuclear Fuel and Reprocessing Waste Inventory, Revision 9
Spent Nuclear Fuel and Reprocessing Waste Inventory, Revision 9
This report provides information on the inventory of spent nuclear fuel (SNF) in the United States located at Nuclear Power Reactor and Independent Spent Fuel Storage Installation sites, as well as SNF and reprocessing waste located at U.S. Department of Energy sites and other research and development centers as of the end of calendar year 2021.
Summary of Consolidated Interim Storage Advantages and Disadvantages from an Integrated Systems Perspective from Prior Reports and Studies
Summary of Consolidated Interim Storage Advantages and Disadvantages from an Integrated Systems Perspective from Prior Reports and Studies
The question of whether centralized storage of civilian spent nuclear fuel (SNF) should be part of the federal waste management system as an intermediate step before permanent disposal has been debated for more than four decades. Centralized storage facilities were included as a potential component of the U.S. spent fuel management system in the Nuclear Waste Policy Act of 1982 (NWPA), but the NWPA did not identify these facilities as being essential.
Yucca Mountain Project Map, YMP–03–024.2, “Proposed Land Withdrawal” July 21, 2005.
Yucca Mountain Project Map, YMP–03–024.2, “Proposed Land Withdrawal” July 21, 2005.
Yucca Mountain Project Map, YMP–03–024.2, “Proposed Land Withdrawal” and dated July 21, 2005. This map is referenced in House of Representatives Bill H.R.3053 — 115th Congress (2017-2018) dated June 26,2017
Science based responses to social myths on nuclear energy
Science based responses to social myths on nuclear energy
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.
From Integral Experiments to Nuclear Data Improvement
From Integral Experiments to Nuclear Data Improvement
Target accuracy on LWR neutronics parameters is 2 to 5 times lower than the a priori uncertainty (1σ)
due to nuclear data. This paper summarizes the experimental facilities and the integral measurements that are required
for code qualification. The rigorous use of integral information through trend analysis method is described. Trends
on JEF2 data from Keff measurements and P.I.Es are presented. These trends were accounted for in the new JEFF3
evaluations. The role of fundamental experiments, such as worth measurement of separated isotopes, is emphasized.
Criticality Evaluation of Degraded Internal Configurations for the PWR AUCF WP Designs
Criticality Evaluation of Degraded Internal Configurations for the PWR AUCF WP Designs
The purpose of this analysis is to provide input on the criticality potential of various degraded configurations to an analysis on the probability of a criticality event in a Pressurized Water Reactor (PWR) Advanced Uncanistered Fuel (AUCF) Waste Package (WP).
Frequency of SNF Misload for Uncanistered Fuel Waste Package
Frequency of SNF Misload for Uncanistered Fuel Waste Package
The purpose of this engineering calculation is to estimate the frequency of misloading spent nuclear fuel (SNF) assemblies that would result in exceeding the criticality design basis of a waste package (WP). This type of misload - a reactivity misload - results from the incorrect placement of one or more fuel assemblies into a waste package such that the criticality controls do not match the required controls for the fuel assemblies. An actual criticality event can not occur in a WP unless a moderator (e.g. water) is present.
In-Drift Precipitates/Salts Model
In-Drift Precipitates/Salts Model
This report documents the development and validation of the in-drift precipitates/salts (IDPS) process model. The IDPS process model is a geochemical model designed to predict the postclosure effects of evaporation and deliquescence on the chemical composition of water within the Engineered Barrier System (EBS) in support of the total system performance assessment (TSPA). Application of the model in support of TSPA is documented in Engineered Barrier System: Physical and Chemical Environment (BSC 2005 [DIRS 175083]).
A Historical Review of the Safe Transport of Spent Nuclear Fuel
A Historical Review of the Safe Transport of Spent Nuclear Fuel
The US Department of Energy (DOE) has since established the IWM, which builds on the work begun by NFST, to develop an integrated waste management system for spent nuclear fuel (SNF)a, including the development of a large-scale transportation system for the safe transport of SNF to storage or disposal facilities.
Fast Flux Test Facility (FFTF) Reactor Fuel Criticality Calculations
Fast Flux Test Facility (FFTF) Reactor Fuel Criticality Calculations
The purpose of these calculations is to characterize the criticality safety concerns for the storage of Fast Flux Test Facility (FFTF) nuclear fuel in a Department of Energy spent nuclear fuel (DOE SNF) canister in a co-disposal waste package. These results will be used to support the analysis that will be done to demonstrate concept viability related to use in the Monitored Geologic Repository (MGR) environment.
DHLW Glass Waste Package Criticality Analysis (SCPB: N/A)
DHLW Glass Waste Package Criticality Analysis (SCPB: N/A)
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to determine the viability of the Defense High-Level Waste (DHLW) Glass waste package concept with respect to criticality regulatory requirements in compliance with the goals of the Waste Package Implementation Plan (Ref. 5.1) for conceptual design. These design calculations are performed in sufficient detail to provide a comprehensive comparison base with other design alternatives.
Criticality Evaluation of Degraded Internal Configurations for a 44 BWR Waste Package
Criticality Evaluation of Degraded Internal Configurations for a 44 BWR Waste Package
The purpose of this calculation is to perform an example criticality evaluation for degraded internal configurations of a boiling water reactor (BWR) waste package (WP) containing 44 spent nuclear fuel (SNF) assemblies.
Description of Fracture Systems for External Criticality Reports
Description of Fracture Systems for External Criticality Reports
The purpose of this Analysis/Model Report (AMR) is to describe probabilistically the main features of the geometry of the fracture system in the vicinity of the repository. They will be used to determine the quantity of fissile material that could accumulate in the fractured rock underneath a waste package as it degrades. This AMR is to feed the geochemical calculations for external criticality reports. This AMR is done in accordance with the technical work plan (BSC (Bechtel SAIC Company) 2001 b). The scope of this AMR is restricted to the relevant parameters of the fracture system.
EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages
EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages
The Monitored Geologic Repository (MGR) Waste Package Operations (WPO) of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Shippingport Pressurized Water Reactor (PWR) (Ref. 1). The Shippingport PWR SNF has been considered for disposal at the proposed Yucca Mountain site.
Isotopic Generation and Confirmation of the BWR Appl. Model
Isotopic Generation and Confirmation of the BWR Appl. Model
The objective of this calculation is to establish an isotopic database to represent commercial spent nuclear fuel (CSNF) from boiling water reactors (BWRs) in criticality analyses performed for the proposed Monitored Geologic Repository at Yucca Mountain, Nevada. Confirmation of the conservatism with respect to criticality in the isotopic concentration values represented by this isotopic database is performed as described in Section 3.5.3.1.2 of the Disposal Criticality Analysis Methodology Topical Report (Reference 7.1).