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Quarterly Progress Report on Fission Product Behavior in LWRs for the Period October-December 1977

Description: Analysis of release data obtained during High Burnup Fuel Test 10 (HBU-10) has been completed. In this test the fuel rod segment was ruptured by internal pressurization at 900/sup 0/C, at which time the temperature was rapidly increased to 1200/sup 0/C and maintained at this temperature for 10 min. Approximately 0.061% of the total cesium inventory in the rod segment was released; this was accompanied by the release of about 1.69% of the total /sup 85/Kr inventory. Moreover, about 0.022% of the… more
Date: February 1, 1978
Creator: Malinauskas, A. P.; Lorenz, R. A.; Collins, J. L.; Osborne, M. F.; Whatley, S. K. & Towns, R. L.
Partner: UNT Libraries Government Documents Department
open access

Energy Measurements in Oxygen-Induced Reactions at 60 A GeV and 200 A GeV

Description: In an effort to isolate characteristic features of nucleus-nucleus collisions (e.g., collective phenomena) from those that may be expected on the basis of a linear superposition of nuelceon-nucleon collisions, we will compare measured quantities with calculations that reproduce data from nucleon-induced reactions and that make predictions for nucleus-nucleus reactions. While several models are available for this procedure, none has yet been demonstrated to have clear advantages over the others.… more
Date: January 1, 1988
Creator: Awes, T. C.; Albrecht, R.; Baktash, C.; Beckmann, P.; Berger, F.; Bock, R. et al.
Partner: UNT Libraries Government Documents Department
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Development of a Laser Optically Pumped Polarized Target for Use in Heavy-Ion Physics

Description: Important micro- and macroscopic details of heavy-ion reactions may be explicitly determined when nuclear spin aligned (polarized) targets are used. For deformed nuclei, the orientation of the symmetry axis of the nuclear density distribution is determined by the nuclear spin orientation. Polarized targets would thus allow experiments to be performed as a function of the orientation of the symmetry axis of the nuclear density distribution. A polarized target of /sup 151/ /sup 153/Eu is being de… more
Date: January 1, 1982
Creator: Shivakumar, B.; Beene, J.R.; Bemis, C.E. Jr.; Erb, K.A.; Ford, J.L.C. Jr. & Shapira, D.
Partner: UNT Libraries Government Documents Department
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Safety Analysis Report for Packaging: The ORNL DOT Specification 6M - Special Form Package

Description: The ORNL DOT Specification 6M - Special Form Package was fabricated at the Oak Ridge Nation al Laboratory (ORNL) for the transport of Type B solid non-fissile radioactive materials in special form. The package was evaluated on the basis of tests performed by the Dow Chemical Company, Rocky Flats Division, on the DOT-6M container and special form tests performed on a variety of stainless steel capsules at ORNL by Operations Division personnel. The results of these evaluations demonstrate that th… more
Date: July 1, 1982
Creator: Schaich, R.W.
Partner: UNT Libraries Government Documents Department
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MHD Activity in the ISX-B Tokamak: Experimental Results and Theoretical Interpretation

Description: The observed spectrum of MHD fluctuations in the ISX-B tokamak is clearly dominated by the n=1 mode when the q=1 surface is in the plasma. This fact agrees well with theoretical predictions based on 3-D resistive MHD calculations. They show that the (m=1; n=1) mode is then the dominant instability. It drives other n=1 modes through toroidal coupling and n>1 modes through nonlinear couplings. These theoretically predicted mode structures have been compared in detail with the experimentally measu… more
Date: January 1, 1982
Creator: Carreras, B. A.; Dunlap, J. L.; Bell, J. D.; Charlton, L. A.; Cooper, W. A.; Dory, R. A. et al.
Partner: UNT Libraries Government Documents Department
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Oak Ridge National Laboratory Shipping Containers for Radioactive Materials

Description: The types of containers used at ORNL for the transport of radioactive materials are described. Both returnable and non-returnable types are included. Containers for solids, liquids and gases are discussed. Casks for the shipment of uranium, irradiated fuel elements, and non-irradiated fuel elements are also described. Specifications are provided. (DC)
Date: May 1, 1980
Creator: Schaich, R.W.
Partner: UNT Libraries Government Documents Department
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Conductors for Tokamak Toroidal Field Coils

Description: This paper describes six conductors which are being developed for use in superconducting toroidal field coils of tokamak fusion machines. Included are three pool boiling and three forced flow concepts. Research and development programs on several of the conductors are under way, jointly involving Oak Ridge National Laboratory (ORNL) and conductor manufacturers. Conductors will be tested in short lengths and in the form of 3m x 2.5m Large Coil Segment (LCS) tests. The conductor development and t… more
Date: January 1, 1977
Creator: Fietz, William A.
Partner: UNT Libraries Government Documents Department
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Note on Graphite Oxidation by Oxygen and Moisture

Description: Simplified equations of graphite oxidation are reviewed for semi-infinite slab, finite slab, and cylinder geometries, using the principal assumptions of linearized oxidation kinetics and quasi-steady state oxidation profile. All equations are coupled to a general surface mass transfer boundary condition. The equations include those for oxidant concentration distribution, surface oxidation rate, burnoff profile, and oxidation efficiency. This review also covers some areas that may not be well re… more
Date: February 1, 2009
Creator: Wichner, Robert; Burchell, Timothy D & Contescu, Cristian I
Partner: UNT Libraries Government Documents Department
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The Role of Demand Resources In Regional Transmission Expansion Planning and Reliable Operations

Description: Investigating the role of demand resources in regional transmission planning has provided mixed results. On one hand there are only a few projects where demand response has been used as an explicit alternative to transmission enhancement. On the other hand there is a fair amount of demand response in the form of energy efficiency, peak reduction, emergency load shedding, and (recently) demand providing ancillary services. All of this demand response reduces the need for transmission enhancement… more
Date: July 1, 2006
Creator: Kirby, Brendan J.
Partner: UNT Libraries Government Documents Department
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PR-EDB: Power Reactor Embrittlement Database - Version 3

Description: The aging and degradation of light-water reactor pressure vessels is of particular concern because of their relevance to plant integrity and the magnitude of the expected irradiation embrittlement. The radiation embrittlement of reactor pressure vessel materials depends on many factors, such as neutron fluence, flux, and energy spectrum, irradiation temperature, and preirradiation material history and chemical compositions. These factors must be considered to reliably predict pressure vessel em… more
Date: March 1, 2008
Creator: Wang, Jy-An John & Subramani, Ranjit
Partner: UNT Libraries Government Documents Department
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Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants

Description: Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Furth… more
Date: August 1, 2007
Creator: Kisner, Roger A; Mullens, James Allen; Wilson, Thomas L; Wood, Richard Thomas; Korsah, Kofi; Qualls, A L et al.
Partner: UNT Libraries Government Documents Department
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Data Compilation for AGR-3/4 Designed-to-Fail (DTF) Fuel Particle Batch LEU04-02DTF

Description: This document is a compilation of coating and characterization data for the AGR-3/4 designed-to-fail (DTF) particles. The DTF coating is a high density, high anisotropy pyrocarbon coating of nominal 20 {micro}m thickness that is deposited directly on the kernel. The purpose of this coating is to fail early in the irradiation, resulting in a controlled release of fission products which can be analyzed to provide data on fission product transport. A small number of DTF particles will be included … more
Date: October 1, 2008
Creator: Hunn, John D & Miller, James Henry
Partner: UNT Libraries Government Documents Department
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A Physically Based Correlation of Irradiation-Induced Transition Temperature Shifts for RPV Steels

Description: The reactor pressure vessels (RPVs) of commercial nuclear power plants are subject to embrittlement due to exposure to high-energy neutrons from the core, which causes changes in material toughness properties that increase with radiation exposure and are affected by many variables. Irradiation embrittlement of RPV beltline materials is currently evaluated using Regulatory Guide 1.99 Revision 2 (RG1.99/2), which presents methods for estimating the shift in Charpy transition temperature at 30 ft-… more
Date: November 1, 2007
Creator: Eason, Ernest D.; Odette, George Robert; Nanstad, Randy K & Yamamoto, Takuya
Partner: UNT Libraries Government Documents Department
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Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 5: Graphite PIRTs

Description: Here we report the outcome of the application of the Nuclear Regulatory Commission (NRC) Phenomena Identification and Ranking Table (PIRT) process to the issue of nuclear-grade graphite for the moderator and structural components of a next generation nuclear plant (NGNP), considering both routine (normal operation) and postulated accident conditions for the NGNP. The NGNP is assumed to be a modular high-temperature gas-cooled reactor (HTGR), either a gas-turbine modular helium reactor (GTMHR) v… more
Date: March 1, 2008
Creator: Burchell, Timothy D; Bratton, Rob; Marsden, Barry; Srinivasan, Makuteswara; Penfield, Scott; Mitchell, Mark et al.
Partner: UNT Libraries Government Documents Department
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Reliability of Current Biokinetic and Dosimetric Models for Radionuclides: A Pilot Study

Description: This report describes the results of a pilot study of the reliability of the biokinetic and dosimetric models currently used by the U.S. Nuclear Regulatory Commission (NRC) as predictors of dose per unit internal or external exposure to radionuclides. The study examines the feasibility of critically evaluating the accuracy of these models for a comprehensive set of radionuclides of concern to the NRC. Each critical evaluation would include: identification of discrepancies between the models and… more
Date: October 1, 2008
Creator: Leggett, Richard Wayne; Eckerman, Keith F & Meck, Robert A.
Partner: UNT Libraries Government Documents Department
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Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel

Description: The purpose of this calculation report, Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel, is to validate the computational method used to perform postclosure criticality calculations. The validation process applies the criticality analysis methodology approach documented in Section 3.5 of the Disposal Criticality Analysis Methodology Topical Report. The application systems for this validation consist of waste packages containing transpor… more
Date: October 1, 2007
Creator: Radulescu, Georgeta; Mueller, Don; Goluoglu, Sedat; Hollenbach, Daniel F & Fox, Patricia B
Partner: UNT Libraries Government Documents Department
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Final Report - Assessment of Potential Phosphate Ion-Cementitious Materials Interactions

Description: The objectives of this limited study were to: (1) review the potential for degradation of cementitious materials due to exposure to high concentrations of phosphate ions; (2) provide an improved understanding of any significant factors that may lead to a requirement to establish exposure limits for concrete structures exposed to soils or ground waters containing high levels of phosphate ions; (3) recommend, as appropriate, whether a limitation on phosphate ion concentration in soils or ground w… more
Date: June 1, 2007
Creator: Naus, Dan J; Mattus, Catherine H & Dole, Leslie Robert
Partner: UNT Libraries Government Documents Department
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Assessment of Fission Product Cross-Section Data for Burnup Credit Applications

Description: Past efforts by the Department of Energy (DOE), the Electric Power Research Institute (EPRI), the Nuclear Regulatory Commission (NRC), and others have provided sufficient technical information to enable the NRC to issue regulatory guidance for implementation of pressurized-water reactor (PWR) burnup credit; however, consideration of only the reactivity change due to the major actinides is recommended in the guidance. Moreover, DOE, NRC, and EPRI have noted the need for additional scientific and… more
Date: December 1, 2007
Creator: Leal, Luiz C.; Derrien, Herve; Dunn, Michael E. & Mueller, Don
Partner: UNT Libraries Government Documents Department
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Validation Testing of Hydrogen Generation Technology

Description: This report describes the results of testing performed by ORNL for Photech Energies, Inc. The objective of the testing was to evaluate the efficacy of Photech's hydrogen generation reactor technology, which produces gaseous hydrogen through electrolysis. Photech provided several prototypes of their proprietary reactor for testing and the ancillary equipment, such as power supplies and electrolyte solutions, required for proper operation of the reactors. ORNL measured the production of hydrogen … more
Date: December 1, 2007
Creator: Smith, Barton & Toops, Todd J
Partner: UNT Libraries Government Documents Department
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Scoping Study on the Safety Impact of Valve Spacing in Natural Gas Pipelines

Description: The U.S. Department of Transportation's Pipeline and Hazardous Materials Safety Administration (PHMSA) is responsible for ensuring the safe, reliable, and environmentally sound operation of the nation's natural gas and hazardous liquid pipelines. Regulations adopted by PHMSA for gas pipelines are provided in 49 CFR 192, and spacing requirements for valves in gas transmission pipelines are presented in 49 CFR 192.179. The present report describes the findings of a scoping study conducted by Oak … more
Date: July 1, 2007
Creator: Sulfredge, Charles David
Partner: UNT Libraries Government Documents Department
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Prediction of External Corrosion for Steel Cylinders--2007 Report

Description: Depleted uranium hexafluoride (DUF{sub 6}) is stored in over 62,000 containment cylinders at the Paducah Gaseous Diffusion Plant (PGDP) in Paducah, Kentucky, and at the Portsmouth Gaseous Diffusion Plant (PORTS) in Portsmouth, Ohio. Over 4,800 of the cylinders at Portsmouth were recently moved there from the East Tennessee Technology Park (ETTP) in Oak Ridge, Tennessee. The cylinders range in age up to 56 years and come in various models, but most are 48-inch diameter 'thin-wall'(312.5 mil) and… more
Date: January 1, 2008
Creator: Schmoyer, Richard L
Partner: UNT Libraries Government Documents Department
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Requirements Definition for ORNL Trusted Corridors Project

Description: The ORNL Trusted Corridors Project has several other names: SensorNet Transportation Pilot; Identification and Monitoring of Radiation (in commerce) Shipments (IMR(ic)S); and Southeastern Transportation Corridor Pilot (SETCP). The project involves acquisition and analysis of transportation data at two mobile and three fixed inspection stations in five states (Kentucky, Mississippi, South Carolina, Tennessee, and Washington DC). Collaborators include the State Police organizations that are respo… more
Date: February 1, 2008
Creator: Walker, Randy M; Hill, David E; Smith, Cyrus M; DeNap, Frank A; White, James D; Gross, Ian G et al.
Partner: UNT Libraries Government Documents Department
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Prototype Weigh-In-Motion Performance

Description: Oak Ridge National Laboratory (ORNL) has developed and patented methods to weigh slowly moving vehicles. We have used this technology to produce a portable weigh-in-motion system that is robust and accurate. This report documents the performance of the second-generation portable weigh-in-motion prototype (WIM Gen II). The results of three modes of weight determination are compared in this report: WIM Gen II dynamic mode, WIM Gen II stop-and-go mode, and static (parked) mode on in-ground, static… more
Date: October 1, 2006
Creator: Abercrombie, Robert K; Beshears, David L; Hively, Lee M; Scudiere, Matthew B & Sheldon, Frederick T
Partner: UNT Libraries Government Documents Department
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Prognostic Analysis of the Tactical Quiet Generator

Description: The U.S. Army needs prognostic analysis of mission-critical equipment to enable condition-based maintenance before failure. ORNL has developed and patented prognostic technology that quantifies condition change from noisy, multi-channel, time-serial data. This report describes an initial application of ORNL's prognostic technology to the Army's Tactical Quiet Generator (TQG), which is designed to operate continuously at 10 kW. Less-than-full power operation causes unburned fuel to accumulate on… more
Date: September 1, 2008
Creator: Hively, Lee M
Partner: UNT Libraries Government Documents Department
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