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DOE standard: Radiological control

Description: The Department of Energy (DOE) has developed this Standard to assist line managers in meeting their responsibilities for implementing occupational radiological control programs. DOE has established regulatory requirements for occupational radiation protection in Title 10 of the Code of Federal Regulations, Part 835 (10 CFR 835), ``Occupational Radiation Protection``. Failure to comply with these requirements may lead to appropriate enforcement actions as authorized under the Price Anderson Act … more
Date: July 1, 1999
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

In situ bioremediation for the Hanford carbon tetrachloride plume. Innovative technology summary report

Description: The 200 Area at Hanford (also called the Central Plateau) contains approximately 817 waste sites, 44 facilities to be demolished, and billions of gallons of contaminated groundwater resulting from chemical processing plants and associated waste facilities (e.g., waste tanks). From 1955 to 1973, carbon tetrachloride, nitrate, and other materials were discharged to subsurface liquid waste disposal facilities in the 200 Area. As much as 600,000 kilograms of carbon tetrachloride may have entered th… more
Date: April 1, 1999
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Centrifugal shot blasting. Innovative technology summary report

Description: At the US Department of Energy (DOE) Fernald Environmental Management Project (FEMP), the Facilities Closure and Demolition Projects Integrated Remedial Design/Remedial Action (RD/RA) work plan calls for the removal of one inch (1 in) depth of concrete surface in areas where contamination with technetium-99 has been identified. This report describes a comparative demonstration between two concrete removal technologies: an innovative system using Centrifugal Shot Blasting (CSB) and a modified ba… more
Date: July 1, 1999
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pipe Explorer{trademark} surveying system. Innovative technology summary report

Description: The US Department of Energy`s (DOE) Chicago Operations Office and the DOE`s Federal Energy Technology Center (FETC) developed a Large Scale Demonstration Project (LSDP) at the Chicago Pile-5 Research Reactor (CP-5) at Argonne National Laboratory-East (ANL). The objective of the LSDP is to demonstrate potentially beneficial decontamination and decommissioning (D and D) technologies in comparison with current baseline technologies. The Pipe Explorer{trademark} system was developed by Science and … more
Date: June 1, 1999
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Position-sensitive radiation monitoring (surface contamination monitor). Innovative technology summary report

Description: The Shonka Research Associates, Inc. Position-Sensitive Radiation Monitor both detects surface radiation and prepares electronic survey map/survey report of surveyed area automatically. The electronically recorded map can be downloaded to a personal computer for review and a map/report can be generated for inclusion in work packages. Switching from beta-gamma detection to alpha detection is relatively simple and entails moving a switch position to alpha and adjusting the voltage level to an alp… more
Date: June 1, 1999
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SRS tank closure. Innovative technology summary report

Description: High-level waste (HLW) tank closure technology is designed to stabilize any remaining radionuclides and hazardous constituents left in a tank after bulk waste removal. Two Savannah River Site (SRS) HLW tanks were closed after cleansing and then filling each tank with three layers of grout. The first layer consists of a chemically reducing grout. The fill material has chemical properties that retard the movement of some radionuclides and chemical constituents. A layer of controlled low-strength … more
Date: August 1, 1999
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DOE Standard: Fire protection design criteria

Description: The development of this Standard reflects the fact that national consensus standards and other design criteria do not comprehensively or, in some cases, adequately address fire protection issues at DOE facilities. This Standard provides supplemental fire protection guidance applicable to the design and construction of DOE facilities and site features (such as water distribution systems) that are also provided for fire protection. It is intended to be used in conjunction with the applicable buil… more
Date: July 1, 1999
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Critical Parameters of Complex Geometry Intersecting Cylinders Containing Uranyl Nitrate Solution

Description: About three dozen previously unreported critical configurations are presented for very complex geometries filled with high concentration enriched uranyl nitrate solution. These geometries resemble a tall, thin Central Column (or trunk of a "tree") having long, thin arms (or "branches") extending up to four directions off the column. Arms are equally spaced from one another in vertical planes; and that spacing ranges from arms in contact to quite wide spacings. Both the Central C… more
Date: June 1, 1999
Creator: Rothe, Robert Emil & Briggs, Joseph Blair
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Calculation of Hydrogen and Oxygen Uptake in Fuel Rod Cladding During Severe Accidents Using the Integral Diffusion Method - Final Design Report

Description: Final 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 cladding oxide … more
Date: June 1, 1999
Creator: Siefken, Larry James
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DIII-D Dust Particulate Characterization (June 1998 Vent)

Description: Dust is a key component of fusion power device accident source term. Understanding the amount of dust expected in fusion power devices and its physical and chemical characteristics is needed to verify assumptions currently used in safety analyses. An important part of this safety research and development work is to characterize dust from existing experimental tokamaks. In this report, we present the collection, data analysis methods used, and the characterization of dust particulate collected f… more
Date: January 1, 1999
Creator: Carmack, William Jonathan
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safety Analyses at the Idaho National Engineering and Environmental Laboratory Test Reactor Area - Past to Present

Description: Test reactors are unique in that the core configuration may change with each operating interval. The process of safety analyses for test reactors at the Idaho National Engineering and Environmental Test Reactor Area has evolved as the computing capabilities, software, and regulatory requirements have changed. The evaluations for experiments and the reactor have moved from measurements in a set configuration and then application to other configurations with a relatively large error to modeling i… more
Date: November 1, 1999
Creator: Ambrosek, Richard Garry & Ingram, Frederick William
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 of 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 visi… more
Date: August 1, 1999
Creator: Shah, Vikram Naginbhai; Ware, Arthur Gates; Atwood, Corwin Lee; Sattison, Martin Blaine; Hartley, Robert Scott & Hsu, C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Crack Growth Monitoring in Harsh Environments by Electric Potential Measurements

Description: Electric potential measurement (EPM) technology offers an attractive alternative to conventional nondestructive evaluation (NDE) for monitoring crack growth in harsh environments. Where conventional NDE methods typically require localized human interaction, the EPM technique developed at the Idaho National Engineering and Environmental Laboratory (INEEL) can be operated remotely and automatically. Once a crack-like defect is discovered via conventional means, EPM can be applied to monitor local… more
Date: September 1, 1999
Creator: Lloyd, Wilson Randolph; Reuter, Walter Graham & Weinberg, David Michael
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Oxidation and Volatilization of TZM Alloy in Air

Description: The excellent high temperature strength and thermal conductivity of molybdenum-base alloys provide attractive features for components in advanced magnetic and inertial fusion devices. Refractory metal base alloys react readily with oxygen and other gases, and molybdenum alloys are susceptible to losses from highly volatile molybdenum trioxide (MoOsub3) species. Transport of radioactivity by the volatilization, migration, and re-deposition of MoO3 during a potential accident involving a loss of … more
Date: October 1, 1999
Creator: Smolik, Galen Richard; Petti, David Andrew & Schuetz, Stanley Thomas
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

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
open access

Issue Management Risk Ranking Systems

Description: Thousands of safety issues have been collected on-line at the Idaho National Engineering and Environmental Laboratory (INEEL) as part of the Issue Management Plan. However, there has been no established approach to prioritize collected and future issues. The authors developed a methodology, based on hazards assessment, to identify and risk rank over 5000 safety issues collected at INEEL. This approach required that it was easily applied and understandable for site adaptation and commensurate wi… more
Date: June 1, 1999
Creator: Novack, Steven David; Marshall, Frances Mc Clellan; Stromberg, Howard Merion & Grant, Gary Michael
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

SCDAP/RELAP5 Lower Core Plate Model

Description: The SCDAP/RELAP5 computer code is a best-estimate analysis tool for performing nuclear reactor severe accident simulations. This report describes the justification, theory, implementation, and testing of a new modeling capability which will refine the analysis of the movement of molten material from the core region to the vessel lower head. As molten material moves from the core region through the core support structures it may encounter conditions which will cause it to freeze in the region of… more
Date: October 1, 1999
Creator: Coryell, Eric Wesley & Griffin, F. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Simplified Risk Model Version II (SRM-II) Structure and Application

Description: The Simplified Risk Model Version II (SRM-II) is a quantitative tool for efficiently evaluating the risk from Department of Energy waste management activities. Risks evaluated include human safety and health and environmental impact. Both accidents and normal, incident-free operation are considered. The risk models are simplifications of more detailed risk analyses, such as those found in environmental impact statements, safety analysis reports, and performance assessments. However, wherever po… more
Date: August 1, 1999
Creator: Eide, Steven Arvid & Wierman, Thomas Edward
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Ventilation Systems Operating Experience Review for Fusion Applications

Description: This report is a collection and review of system operation and failure experiences for air ventilation systems in nuclear facilities. These experiences are applicable for magnetic and inertial fusion facilities since air ventilation systems are support systems that can be considered generic to nuclear facilities. The report contains descriptions of ventilation system components, operating experiences with these systems, component failure rates, and component repair times. Since ventilation syst… more
Date: December 1, 1999
Creator: Cadwallader, Lee Charles
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spent Nuclear Fuel Dry Transfer System Cold Demonstration Project Final Report

Description: The spent nuclear fuel dry transfer system (DTS) provides an interface between large and small casks and between storage-only and transportation casks. It permits decommissioning of reactor pools after shutdown and allows the use of large storage-only casks for temporary onsite storage of spent nuclear fuel irrespective of reactor or fuel handling limitations at a reactor site. A cold demonstration of the DTS prototype was initiated in August 1996 at the Idaho National Engineering and Environme… more
Date: December 1, 1999
Creator: Christensen, Max R & McKinnon, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Heat Transfer Model for a Stratified Corium-metal Pool in the Lower Plenum of a Nuclear Reactor

Description: This preliminary design report describes a model for heat transfer in a corium-metal stratified pool. It was decided to make use of the existing COUPLE model. Currently available correlations for natural convection heat transfer in a pool with and without internal heat generation were obtained. The appropriate correlations will be incorporated in the existing COUPLE model. Heat conduction and solidification modeling will be done with existing algorithms in the COUPLE. Assessment of the new mode… more
Date: August 1, 1999
Creator: Sohal, Manohar Singh & Siefken, Larry James
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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INEEL Worker Involvement as a Means of Controlling Their Own Safety

Description: Using the eight guiding principles of Integrated Safety Management (ISM) - Worker Involvement - will move the work force on a forward path from just doing work to doing work safely. This path can be achieved by changing the safety culture in the work place. The work force is more likely to accept a process that will allow them to be accountable for their own safety if they feel ownership through Worker Involvement. The marrying of the Voluntary Protection Program (VPP) and ISM will give workers… more
Date: May 1, 1999
Creator: Fox, David Harold & Hein, Curt David
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Review of ENDF/B-VI Fission-Product Cross Section

Description: In response to concerns raised in the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 93-2, the U.S. Department of Energy (DOE) developed a comprehensive program to help assure that the DOE maintain and enhance its capability to predict the criticality of systems throughout the complex. Tasks developed to implement the response to DNFSB recommendation 93-2 included Critical Experiments, Criticality Benchmarks, Training, Analytical Methods, and Nuclear Data. The Nuclear Data Task … more
Date: January 1, 1999
Creator: Wright, R.Q.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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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