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Nuclear Criticality Calculations for Canister-Based Facilities- Commercial SNF
Nuclear Criticality Calculations for Canister-Based Facilities- Commercial SNF
The purpose of this calculation is to perform waste-form specific nuclear criticality safety calculations to aid in establishing criticality safety design criteria, and to identify design and process parameters that are potentially important to the criticality safety of the transportation, aging and disposal (TAD) canister-based systems.
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. The BWR assembly design considered is based on the General Electric (GE) 8x8 assembly (see section 5.1). Depletion analyses for various assembly average enrichment and burnup (expressed as gigawatt days/metric ton Uranium; GWd/MTU) combinations are performed using the SAS2H/ORIGEN-S sequence of SCALE 4.3 (CSCI:30011-2002; Ref. 7.5).
Frequency and Quality of Radiation Monitoring of Construction Workers at Two Gaseous Diffusion Plants
Frequency and Quality of Radiation Monitoring of Construction Workers at Two Gaseous Diffusion Plants
Construction workers were and are considered temporary workers at many construction sites. Since WWII, large numbers of construction workers were employed at US DOE nuclear weapons sites for periods ranging from a few days to over 30 years. These workers performed tasks during new construction and maintenance, repair, renovation, and demolition of existing facilities.
Aging Facility Criticality Safety Calculations
Aging Facility Criticality Safety Calculations
This design calculation is a revision of the previous criticality evaluation of the operations and
processes that are performed in the Aging Facility. It will also demonstrate and assure that the
storage and aging operations to be performed in the Aging Facility meet the criticality safety
design criteria in the Project Design Criteria Document (BSC 2005i, Section 4.9.2.2), and the
nuclear criticality safety requirements described in the SNF Aging System Description Document
MRS Siting Briefing
MRS Siting Briefing
This briefing paper is a component of the comprehensive briefing package developed for the Negotiator, and describes previous DOE experience in its attempt to site an MRS facility. The Background section highlights, in chronological order, significant events in DOE's MRS siting history from enactment of the Nuclear Waste Policy Act of 1982 to the issuance of the "Report to Congress on Reassessment of the Civilian Radioactive Waste Management Program" in November 1989.
slides - Transportation Planning Considerations: BRC Report Recommendations and Plans for Implementation
slides - Transportation Planning Considerations: BRC Report Recommendations and Plans for Implementation
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Historical Summary of the Three Mile Island Unit 2 Core Debris Transportation Campaign
Historical Summary of the Three Mile Island Unit 2 Core Debris Transportation Campaign
Transport of the damaged core materials from the Unit 2 reactor of the Three
Mile Island Nuclear Power Station (TMI-2) to the Idaho National Engineering Laboratory
(INEL) for examination and storage presented many technical and institutional
challenges, including assessing the ability to transport the damaged core;
removing and packaging core debris in ways suitable for transport; developing a
transport package that could both meet Federal regulations and interface with the
Slides - Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste
Slides - Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste
Presented at the 10th Meeting of the U.S.-Argentina Joint Standing Committee on Nuclear Energy Cooperation, Oak Ridge, Tennessee, August 26, 2013
slides - Transportation Readiness
slides - Transportation Readiness
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - LACBWR Dry Cask Storage
slides - LACBWR Dry Cask Storage
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS)
Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS)
Slides - 2014 WM Symposia, March 2-6, 2014, Phoenix, AZ
Review of Axial Burnup Distribution Considerations for Burnup Credit Calculations
Review of Axial Burnup Distribution Considerations for Burnup Credit Calculations
This report attempts to summarize and consolidate the existing knowledge on axial
burnup distribution issues that are important to burnup credit criticality safety calculations.
Recently released Nuclear Regulatory Commission (NRC) staff guidance permits limited burnup
credit, and thus, has prompted resolution of the axial burnup distribution issue. The reactivity
difference between the neutron multiplication factor (keff) calculated with explicit representation
Features, Events, and Processes for the Total System Performance Assessment: Methods
Features, Events, and Processes for the Total System Performance Assessment: Methods
The purpose of this methods report is to document: (1) the origin, and the methods used in the development of a comprehensive list of features, events, and/or processes (FEPs) that could potentially affect the postclosure performance of the Yucca Mountain disposal system; (2) the methodology and guidance used to screen FEPs for inclusion or exclusion from Total System Performance Assessment for the License Application (TSPA-LA) analysis; (3) the methodology and guidance used to create scenario classes; and (4) compliance with NUREG-1804 (NRC 2003.
Centralized InterimStorage Facility Topical Safety Report
Centralized InterimStorage Facility Topical Safety Report
The Centralized Interim Storage Facility (CISF) is designed as a temporary, above-ground away-from-reactor spent fuel storage installation for up to 40,000 metric tons of uranium (MTU). The design is non-site-specific but incorporates conservative environmental and design factors (e.g., 360 mph tornado and 0.75 g seismic loading) intended to be capable of bounding subsequent site-specific factors. Spent fuel is received in dual-purpose canister systems and/or casks already approved for transportation and storage by the Nuclear Regulatory Commission (NRC).
Preclosure Criticality Safety Analysis
Preclosure Criticality Safety Analysis
The means to prevent and control criticality must be addressed as part of the Preclosure Safety Analysis (PCSA) required for compliance with 10 CFR Part 63 [DIRS 180319], where the preclosure period covers the time prior to permanent closure activities. This technical report presents the nuclear criticality safety evaluation that documents the achievement of this objective.
slides - Advancing the Used Fuel Management Agenda
slides - Advancing the Used Fuel Management Agenda
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Public Beliefs, Concerns and Preferences Regarding the Management of Used Nuclear Fuel and High Level Radioactive Waste
Public Beliefs, Concerns and Preferences Regarding the Management of Used Nuclear Fuel and High Level Radioactive Waste
US policy for management of used nuclear fuel (UNF) and high level radioactive wastes (HLRW) is at a crossroads, and the success of new policy directions will depend in part on broad public acceptance and support. In this paper I provide an overview of the evidence concerning the beliefs and concerns of members of the American public regarding UNF and HLNW. I also characterize the evidence on American’s policy preferences for management of these materials.
Long-Term Criticality Control Issues for the MPC
Long-Term Criticality Control Issues for the MPC
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) in response to a request received via a QAP-3-12 Design Input Data Request (Reference 5.1) from Waste Acceptance, Storage, & Transportation (WAST) Design (formerly MRSMPC Design). This design analysis is an answer to the Design Input Data Request to provide: Specific requirements for long-term criticality control.
slides - ISFSI Security Rulemaking Update
slides - ISFSI Security Rulemaking Update
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Determination of the Accuracy of Utility Spent Fuel Burnup Records (Interim Report)
Determination of the Accuracy of Utility Spent Fuel Burnup Records (Interim Report)
This report summarizes the results of an initial investigation into the uncertainties associated with the burnup records maintained by nuclear power plants. The results indicate that there is an overall uncertainty of about 2 percent in the burnup records, which must be accounted for in spent fuel applications.
CONSIDERATIONS FOR AN INTEGRATED STORAGE, TRANSPORTATION, AND DISPOSAL CANISTER
CONSIDERATIONS FOR AN INTEGRATED STORAGE, TRANSPORTATION, AND DISPOSAL CANISTER
Direct disposal of the large canisters currently being used by the commercial nuclear power industry is beyond the current experience base domestically and internationally and potentially represents many other significant engineering and scientific challenges. Pragmatically, it is reasonable to assume that the packages that will be disposed of in the future may be significantly different from what is being used for storage today.
Fast Flux Test Facility (FFTF) Reactor Fuel Degraded Criticality Calculation: Degraded SNF Canister
Fast Flux Test Facility (FFTF) Reactor Fuel Degraded Criticality Calculation: Degraded SNF Canister
The objective of this calculation is to characterize the criticality aspect of a Department of Energy Spent Nuclear Fuel (DOE SNF) canister containing 5 Fast Flux Test Facility (FFTF) assemblies in a Five-Pack Defense High-Level Waste (HLW) waste package(WP). The purpose of this calculation is to investigate the criticality issues for the WP containg HLW and DOE SNF canisters in various stages of degradation. The calculational method used to perform the criticality calculations consisted of using the MNCP Version 4B2 (Ref.
Route Identification Project: Final Report to the U.S. Department of Energy's Office of Civilian Radioactive Waste Management
Route Identification Project: Final Report to the U.S. Department of Energy's Office of Civilian Radioactive Waste Management
The member states of the Council of State Governments' Midwestern Radioactive Materials Transportation Committee feel that route selection for shipments under the Nuclear Waste Policy Act (NWPA) should begin with a regional review of available routes, since states are in a better position than the federal government to judge the quality of potential highway and rail routes through their jurisdictions. Through its cooperative agreement with the U.S.
Strategies for Application of Isotopic Uncertainties in Burnup Credit
Strategies for Application of Isotopic Uncertainties in Burnup Credit
Uncertainties in the predicted isotopic concentrations in spent nuclear fuel represent one of the largest
sources of overall uncertainty in criticality calculations that use burnup credit. The methods used to
propagate the uncertainties in the calculated nuclide concentrations to the uncertainty in the predicted
neutron multiplication factor (keff) of the system can have a significant effect on the uncertainty in the
safety margin in criticality calculations and ultimately affect the potential capacity of spent fuel transport