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Thermal Analysis of the 9975 Package with the 3013 Configuration During Normal Conditions of Transport

Description: Thermal analysis of the 9975 package with three configurations of the BNFL 3013 outer container (with Rocky Flats, SRS, and BNFL inner containers) have been performed for Normal Conditions of Transport (NCT) of plutonium oxide and metal. The NCT is defined in 10 CFR 71.71(c)(1) s an ambient of 100 F (38 C) in still air with 800 W/m{sup 2} and 400 W/m{sup 2} of solar heating on the drum top and sides, respectively. The 9975 drum package is considered to be in an upright position, and the drum bo… more
Date: February 22, 1999
Creator: Hensel, S
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Models for the Configuration and Integrity of Partially Oxidized Fuel Rod Cladding at High Temperatures - Final Design Report

Description: Models were designed to resolve deficiencies in the SCDAP/RELAP5/MOD3.2 calculations of the configuration and integrity of hot, partially oxidized cladding. The modeling was improved in five areas. First, the configuration defined for melted metallic cladding retained by an adjacent oxide layer was improved. Second, the empirical model to account for the effect on oxidation of intact cladding is not significantly reduced by the presence of a rather high concentration of relocated material. Thir… more
Date: February 1, 1999
Creator: Siefken, Larry James
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Design Report for Modeling of Hydrogen Uptake in Fuel Rod Cladding During Severe Accidents

Description: Preliminary designs are described for models of hydrogen and oxygen uptake in fuel rod cladding during severe accidents. Calculation of the uptake involves the modeling of seven processes: (1) diffusion of oxygen from the bulk gas into the boundary layer at the external cladding surface, (2) diffusion from the boundary layer into the oxide layer, (3) diffusion from the inner surface of the oxide layer into the metallic part of the cladding, (4) uptake of hydrogen in the event that the clad-ding… more
Date: February 1, 1999
Creator: Siefken, Larry James
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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National Low-Level Waste Management Program Radionuclide Report Series

Description: The National Low Level Waste Management Program at the Idaho National Engineering and Environmental Laboratory has published a report containing key information about selected radionuclides that are most likely to contribute significantly to the radiation exposures estimated from a performance assessment of a low-level radioactive waste (LLW) disposal facility. The information includes physical and chemical characteristics, production means, waste forms, behavior of the radionuclide in soils, p… more
Date: February 1, 1999
Creator: Adams, J.P.; Carboneau, M.L. & Allred, W.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Pressure vessels and piping systems: general requirements and documentation for testing

Description: Pressure vessel and piping systems are widely used throughout industry and research laboratories and contain a very large concentration of energy, and yet, despite the fact that their design and installation comply with federal, state and local regulations and recognized industrial standards, there continue to be serious pressure equipment failures. There are many reasons for pressure equipment failure: degradation and thinning of materials with usage, aging, hidden flaws during fabrication, et… more
Date: February 25, 1999
Creator: Blyukher, B; Borzileri, C; Brailovsky, Y & Tsicalo, A
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Assessment of Field Experience Related to Pressurized Water Reactor Primary System Leaks

Description: This paper presents our assessment of field experience related to pressurized water reactor (PWR) primary system leaks in terms of their number and rates, how aging affects frequency of leak events, the safety significance of such leaks, industry efforts to reduce leaks, and effectiveness of current leak detection systems. We have reviewed the licensee event reports to identify the events that took place during 1985 to the third quarter of 1996, and reviewed related technical literature and vis… more
Date: February 1, 1999
Creator: Shah, Vikram N.; Ware, Arthur G.; Atwood, Cory L.; Sattison, Martin B.; Hartley, R. Scott & Hsu, Chuck
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Subcritical Noise Analysis Measurements with Fresh and Spent Research Reactor Fuels Elements

Description: The verification of the subcriticality is of utmost importance for the safe transportation and storage of nuclear reactor fuels. Transportation containers and storage facilities are designed such that nuclear fuels remain in a subcritical state. Such designs often involve excess conservatism because of the lack of relevant experimental data to verify the accuracy of Monte Carlo codes used in nuclear criticality safety analyses. A joint experimental research program between Oak Ridge National La… more
Date: February 1, 1999
Creator: Valentine, T. E.; Mihalczo, J. T.; Kryter, R. C. & Miller, V. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Photovoltaic Energy Program Contract Summary; Fiscal Year 1998

Description: This document provides individual summaries of some 200 photovoltaics research projects performed in house and by subcontractors to Department of Energy national laboratories and field offices, including the National Renewable Energy Laboratory, Sandia National Laboratories, Golden Field Office, Brookhaven National Laboratory, Albuquerque Field Office, and Boston Support Office. The document is divided into the following sections: research and development, technology development, and systems en… more
Date: February 16, 1999
Creator: Surek, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safety analysis approaches or mixed transuranic waste.

Description: Argonne National Laboratory (ANL) has completed a survey of assumptions and techniques used for safety analyses at seven sites that handle or store mixed transuranic (TRU) waste operated by contractors for the US Department of Energy (DOE). While approaches to estimating on-site and off-site consequences of hypothetical accidents differ, there are commonalities in all of the safety studies. This paper identifies key parameters and methods used to estimate the radiological consequences associate… more
Date: February 10, 1999
Creator: Courtney, J. C.; Dwight, C. C.; Forrester, R. J.; Lehto, M. A. & Pan, Y. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Measurement of plutonium and other actinide elements at the center for accelerator mass spectrometry: a comparative assessments of competing techniques

Description: Low-level measurements of the long-lived actinide isotopes have a number of important applications throughout the DOE complex. These include radiobioassay programs, environmental assessments, characterization of radioactive wastes, evaluation of waste storage and treatment options, environmental remediation, basic research in chemistry and geochemistry, and other specialized non- proliferation and national security applications. As an example, it has been estimated that for the next few decades… more
Date: February 1, 1999
Creator: Hamilton, T. F. & McAninch, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spent nuclear fuel project - criteria document spent nuclear fuel final safety analysis report

Description: The criteria document provides the criteria and planning guidance for developing the Spent Nuclear Fuel (SNF) Final Safety Analysis Report (FSAR). This FSAR will support the US Department of Energy, Richland Operations Office decision to authorize the procurement, installation, installation acceptance testing, startup, and operation of the SNF Project facilities (K Basins, Cold Vacuum Drying Facility, and Canister Storage Building).
Date: February 23, 1999
Creator: Morgan, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Lung cancer risk of low-level exposures to alpha emitters: critical reappraisal and experiments based on a new cytodynamic model

Description: Ecologic U.S. county data suggest negative associations between residential radon exposure and lung cancer mortality (LCM)-inconsistent with clearly positive associations revealed by occupational data on individual miners, but perhaps explained by competing effects of cell killing vs. mutations in alpha-exposed bronchial epithelium. To assess the latter possibility, a biologically based �cytodynamic 2-stage� (CD2) cancer-risk model was fit to combined 1950-54 age- specific person-year data on l… more
Date: February 20, 1999
Creator: Bogen, K T
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 1998

Description: This is the ninth Annual Report to the Congress describing Department of Energy (Department) activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of energy regarding public health and safety issues at the Department`s defense nuclear facilities. The Board also reviews and evaluates the content and… more
Date: February 1, 1999
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Comparison of High-Voltage Switches

Description: This report summarizes our work on high-voltage switches during the past few years. With joint funding from the Department of Energy (DOE) and the Department of Defense (DOD), we tested a wide variety of switches to a common standard. This approach permitted meaningful comparisons between disparate switches. Most switches were purchased from commercial sources, though some were experimental devices. For the purposes of this report, we divided the switches into three generic types (gas, vacuum, … more
Date: February 1, 1999
Creator: Chu, K. W. & Scott, G. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radiation Physics for Personnel and Environmental Protection

Description: The Fermi National Accelerator Laboratory FERMILAB- TM- 1834 Fermi National Accelerator Laboratory This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or repres… more
Date: February 15, 1999
Creator: Cossairt, J.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Idaho National Engineering and Environmental Laboratory Radiological Control Performance Indicator Report -- Fourth Quarter, Calendar Year 1998

Description: This document provides a report of an analysis of the Radiological Control Program through the fourth quarter of Calendar Year (CY-98) and is the annual report for the Idaho National Engineering and Environmental Laboratory (INEEL). This Performance Indicator Report is provided in accordance with Article 133 of the INEEL Radiological Control Manual. The INEEL collective occupational radiation deep dose is 63.034 person-rem year to date, compared to a goal of 83.1 person-rem. During the fourth q… more
Date: February 1, 1999
Creator: Hinckley, F.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Spent nuclear fuel project cold vacuum drying facility safety equipment list

Description: This document provides the safety equipment list (SEL) for the Cold Vacuum Drying Facility (CVDF). The SEL was prepared in accordance with the procedure for safety structures, systems, and components (SSCs) in HNF-PRO-516, ''Safety Structures, Systems, and Components,'' Revision 0 and HNF-PRO-097, Engineering Design and Evaluation, Revision 0. The SEL was developed in conjunction with HNF-SO-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installatio… more
Date: February 24, 1999
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fire hazard analysis for Plutonium Finishing Plant complex

Description: A fire hazards analysis (FHA) was performed for the Plutonium Finishing Plant (PFP) Complex at the Department of Energy (DOE) Hanford site. The scope of the FHA focuses on the nuclear facilities/structures in the Complex. The analysis was conducted in accordance with RLID 5480.7, [DOE Directive RLID 5480.7, 1/17/94] and DOE Order 5480.7A, ''Fire Protection'' [DOE Order 5480.7A, 2/17/93] and addresses each of the sixteen principle elements outlined in paragraph 9.a(3) of the Order. The elements … more
Date: February 23, 1999
Creator: MCKINNIS, D.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CSER 98-003: Criticality safety evaluation report for PFP glovebox HC-21A with button can opening

Description: Glovebox HC-21A is an enclosure where cans containing plutonium metal buttons or other plutonium bearing materials are prepared for thermal stabilization in the muffle furnaces. The Inert Atmosphere Confinement (IAC), a new feature added to Glovebox HC-21A, allows the opening of containers suspected of containing hydrided plutonium metal. The argon atmosphere in the IAC prevents an adverse reaction between oxygen and the hydride. The hydride is then stabilized in a controlled manner to prevent … more
Date: February 23, 1999
Creator: Erickson, D. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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System design description PFP thermal stabilization

Description: The purpose of this document is to provide a system design description and design basis for the Plutonium Finishing Plant (PFP) Thermal Stabilization project. The sources of material for this project are residues scraped from glovebox floors and materials already stored in vault storage that need further stabilizing. Stabilizing this material will promote long term storage and reduced worker exposure. This document addresses: functional design, equipment, and safety requirements for thermal sta… more
Date: February 23, 1999
Creator: LARKIN, K.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tank characterization report for single-shell tank 241-BX-110

Description: A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-BX-110. The objectives of this report are (1) to use characterization data in response to technical issues… more
Date: February 23, 1999
Creator: RASMUSSEN, J.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Canister storage building design basis accident analysis documentation

Description: This document provides the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.
Date: February 25, 1999
Creator: KOPELIC, S.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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