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The safety record at the tritium systems test assembly

Description: This work addresses an important objective of the TSTA-demonstrating that the large tritium inventories required for fusion reactors can be routinely handled, without radiation exposure to operating personnel and without significant environemtnal releases. The techniques by which TSTA has achieved low releases and personnel exposures include high-integrity primary piping systems that exclude contact between tritium and organic materials, a secondary containment system that encloses all primary … more
Date: February 1, 1988
Creator: Coffin, D.O.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A study of steady-state steam-water counterflow in porous media

Description: Vapor-liquid counterflow in porous media arises in processes such as heat pipes, oil recovery and geothermal systems. Previous studies analysed these phenomena in separate contexts. This paper presents a unified description from which previous models result as limiting cases. The analysis includes capillarity, heat conduction, and Kelvin effects. The importance of each term to various processes is examined. Significantly, it is found that the critical heat flux is not constant but increases wit… more
Date: February 1, 1990
Creator: Satik, C.; Parlar, M. & Yortsos, Y.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Validated heat-transfer and pressure-drop prediction methods based on the discrete element method: Phase 1, Three-dimensiional roughness

Description: A computer program based on the discrete element method has been developed and validated to compute friction factors and Nusselt numbers for fully developed turbulent flow and heat transfer in pipes with three-dimensional roughness elements. Computational results are compared with appropriate cases from heat transfer experiments in the literature. The predictions were in general in very good agreement with the experimental data.
Date: February 1, 1992
Creator: Taylor, R.P. & Hodge, B.K. (Mississippi State Univ., MS (United States). Dept. of Mechanical and Nuclear Engineering)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measured residual stresses in overlay pipe weldments removed from service

Description: Surface and throughwall residual stresses were measured on an elbow-to-pipe weldment that had been removed from the Hatch-2 reactor about a year after the application of a weld overlay. The results were compared with experimental measurements on three mock-up weldments and with finite-element calculations. The comparison shows that there are significant differences in the form and magnitude of the residual stress distributions. However, even after more than a year of service, the residual stres… more
Date: February 1, 1985
Creator: Shack, W.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Texasgulf solar cogeneration program. Mid-term topical report

Description: The status of technical activities of the Texasgulf Solar Cogeneration Program at the Comanche Creek Sulfur Mine is described. The program efforts reported focus on preparation of a system specification, selection of a site-specific configuration, conceptual design, and facility performance. Trade-off studies performed to select the site-specific cogeneration facility configuration that would be the basis for the conceptual design efforts are described. Study areas included solar system size, t… more
Date: February 1, 1981
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Coal Technology Program. Progress report for December 1977

Description: In the pressure vessel and piping materials work, the report, ''Assessment of Materials Technology for Gasifer and Reaction Pressure Vessels and Piping for Second Generation Commercial Coal Conversion Systems'' (ORNL-5238), has been submitted for publication and distribution. Impact and tensile teting is under way on 2/sup 1///sub 4/ cr-1 Mo steel which has received a simulated quench, temper, and postweld heat treatment. Two topical reports on coating inspection have gone to reproduction. CoCr… more
Date: February 1, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LOFT emergency core coolant thermal analysis Class I review

Description: The LOFT Emergency Core Coolant Piping Thermal Analysis was checked to insure that the calculations made would conservatively satisfy the requirements in the LOFT technical specifications. Some of the boundary conditions used have not been shown to be conservative and require review and possible re-analysis. One of the thermal models used could not be clearly related to a specific part of the piping geometry and requires further explanation. The remainder of the models, the use of the SIMIR cod… more
Date: February 3, 1978
Creator: Kinnaman, T.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LOFT blowdown loop piping thermal analysis Class I review

Description: In accordance with ASME Code, Section III requirements, all analyses of Class I components must be independently reviewed. Since the LOFT blowdown loop piping up through the blowdown valve is a Class I piping system, the thermal analyses are reviewed. The Thermal Analysis Branch comments to this review are also included. It is the opinion of the Thermal Analysis Branch that these comments satisfy all of the reviewers questions and that the analyses should stand as is, without additional conside… more
Date: February 14, 1978
Creator: Kinnaman, T.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Failure probability of PWR reactor coolant loop piping. [Double-ended guillotine break]

Description: This paper describes the results of assessments performed on the PWR coolant loop piping of Westinghouse and Combustion Engineering plants. For direct double-ended guillotine break (DEGB), consideration was given to crack existence probability, initial crack size distribution, hydrostatic proof test, preservice inspection, leak detection probability, crack growth characteristics, and failure criteria based on the net section stress failure and tearing modulus stability concept. For indirect DEG… more
Date: February 1, 1984
Creator: Lo, T.; Woo, H.H.; Holman, G.S. & Chou, C.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF FREEZE VALVE FOR USE IN THE MSRE

Description: Three types of frozen-seal valves'' were tested for possible use in the MSRE. The seal was melted by direct resistance heat, by induction heat, and by clamp-on Calrod heat. The frozen seal was made in a preformed restriction section of a standard piece of pipe by a cooling-gas jet stream directed at the restriction. All three valves performed satisfactorily through 100 test cycles. The Calrodheated valve was selected for MSRE use on the basis of simplicity of design and of operation. Two of the… more
Date: February 28, 1962
Creator: Richardson, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Conceptual design study FY 1981: synfuels from fusion - using the tandem mirror reactor and a thermochemical cycle to produce hydrogen

Description: This report represents the second year's effort of a scoping and conceptual design study being conducted for the express purpose of evaluating the engineering potential of producing hydrogen by thermochemical cycles using a tandem mirror fusion driver. The hydrogen thus produced may then be used as a feedstock to produce fuels such as methane, methanol, or gasoline. The main objective of this second year's study has been to obtain some approximate cost figures for hydrogen production through a … more
Date: February 9, 1982
Creator: Krikorian, O.H. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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OTEC cold water pipe: a survey of available shell analysis computer programs and implications of hydrodynamic loadings

Description: The design and analysis of the cold water pipe (CWP) is one of the most important technological problems to be solved in the OTEC ocean engineering program. Analytical computer models have to be developed and verified in order to provide an engineering approach for the OTEC CWP with regards to environmental factors such as waves, currents, platform motions, etc., and for various structural configurations and materials such as rigid wall CWP, compliant CWP, stockade CWP, etc. To this end, Analys… more
Date: February 1, 1979
Creator: Pompa, J. A.; Allik, H.; Webman, K. & Spaulding, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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San Onofre/Zion auxiliary feedwater system seismic fault tree modeling

Description: As part of the study for the seismic evaluation of the San Onofre Unit 1 Auxiliary Feedwater System (AFWS), a fault tree model was developed capable of handling the effect of structural failure of the plant (in the event of an earthquake) on the availability of the AFWS. A compatible fault tree model was developed for the Zion Unit 1 AFWS in order to compare the results of the two systems. It was concluded that if a single failure of the San Onofre Unit 1 AFWS is to be prevented, some weight ex… more
Date: February 1, 1982
Creator: Najafi, B. & Eide, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Review of reports associated with systems of the K, P and L reactors at the Savannah River Site

Description: Six reports associated with the structural integrity of several systems of the Savannah River Site reactors are reviewed. The focus is on the materials-related aspects of the reports and no attempt is made to address the stress analysis-related issues.
Date: February 1, 1992
Creator: Cowgill, M. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Evaluation of a Portable Handheld Combined Gamma and Neutron Directional Isotopic Identifying Detector

Description: Purpose: To simulate the performance of a portable dual gamma and neutron identification detector array with dual directional detection capability for preliminary algorithm evaluation. Experimental procedures: Monte Carlo N-Particle (MCNP) analysis on a compact array of borated polyvinyl toluene light pipes and photomultiplier tubes, standard spectral histogramming, and directional detection capability simulations. Results: Results demonstrate that the detector system is fully capable of correc… more
Date: February 14, 2008
Creator: Hayes, Robert
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Load rating and design criteria for pipe snubbers with extension struts

Description: Snubbing devices are used extensively in nuclear power plant piping to prevent seismic shock forces from causing damaging pipe motions. Most seismic snubbers are designed and load rated by the manufacturer without consideration of attaching structure, unless specifically requested to do so by the purchaser. This paper discusses the additional design constraints imposed by the use of extension struts with the seismic snubbers. The constraints evaluated include load rating reduction as a function… more
Date: February 1, 1979
Creator: Entz, R. D. & Anderson, M. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reserve seismic capacity determination of a nuclear power plant braced frame with piping

Description: A typical diagonal braced steel frame was developed to determine the amount of reserve capacity that is available beyond elastic design levels. The frame was analyzed first using elastic static and dynamic analyses. The loadings included dead and live load, an equivalent static lateral earthquake load, two response spectra and a suite of eight earthquake time history records. The response spectra used were the Housner and Regulatory Guide 1.60. The time histories represented different site cond… more
Date: February 27, 1979
Creator: Nelson, T.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Concrete polymer materials as alternate materials of construction for geothermal applications - field test evaluations

Description: A serious problem in the development of geothermal energy is the availability of durable and economical materials of construction for handling hot brine and steam. Hot brine and other aerated geothermal fluids are highly corrosive and they attack most conventional materials of construction. Brookhaven National Laboratory has been investigating the use of concrete polymer materials as alternate materials of construction for geothermal processes. To date, successful field tests have been demonstr… more
Date: February 2, 1979
Creator: Fontana, J.J. & Zeldin, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Seismic analysis response factors and design margins of piping systems

Description: Median response and its variability and correlation are the elements required in the calculation of component failure probability. Conservatism or non-conservatism of the seismic response of piping system generated by the plant design procedures must be removed. The Lawrence Livermore National Laboratory under contract to the US Nuclear Regulatory Commission developed an overall seismic risk assessment methodology which was applied to the seismic probabilistic risk assessment at the Zion Nuclea… more
Date: February 1, 1985
Creator: Shieh, L.C.; Tsai, N.C.; Yang, M.S. & Wong, W.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Design analysis of liquid metal pipe supports

Description: Design guidelines pertinent to liquid metal pipe supports are presented. The numerous complex conditions affecting the support stiffness and strength are addressed in detail. Topics covered include modeling of supports for natural frequency and stiffness calculations, support hardware components, formulas for deflection due to torsion, plate bending, and out-of-plane flexibility. A sample analysis and a discussion on stress analysis of supports are included. Also presented are recommendations f… more
Date: February 1, 1979
Creator: Margolin, L.L. & LaSalle, F.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Heat pipe cooling system for underground, radioactive waste storage tanks

Description: An array of 37 heat pipes inserted through the central hole at the top of a radioactive waste storage tank will remove 100,000 Btu/h with a heat sink of 70/sup 0/F atmospheric air. Heat transfer inside the tank to the heat pipe is by natural convection. Heat rejection to outside air utilizes a blower to force air past the heat pipe condenser. The heat pipe evaporator section is axially finned, and is constructed of stainless steel. The working fluid is ammonia. The finned pipes are individually… more
Date: February 1, 1980
Creator: Cooper, K. C. & Prenger, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Subsystem response determination for the US NRC Seismic Safety Margins Research Program

Description: The initial portion of the task described deals with a definition of the state-of-the-art of seismic qualification methods for subsystems. Too facilitate treatment of this broad class of subsystems, three classifications have been identified: multiply supported subsystems (e.g., piping systems); mechanical components (e.g., valves, pumps, control rod drives, hydraulic systems, etc.); and electrical components (e.g., electrical control panels). Descriptions of the available analysis and/or testi… more
Date: February 22, 1979
Creator: Johnson, J. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Seismic fragility test of a 6-inch diameter pipe system

Description: This report contains the test results and assessments of seismic fragility tests performed on a 6-inch diameter piping system. The test was funded by the US Nuclear Regulatory Commission (NRC) and conducted by ETEC. The objective of the test was to investigate the ability of a representative nuclear piping system to withstand high level dynamic seismic and other loadings. Levels of loadings achieved during seismic testing were 20 to 30 times larger than normal elastic design evaluations to ASME… more
Date: February 1, 1987
Creator: Chen, W. P.; Onesto, A. T. & DeVita, V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Examination of overlay pipe weldments removed from the Hatch-2 reactor

Description: Laboratory ultrasonic examination (UT), dye penetrant examination (PT), metallography, and sensitization measurements were performed on Type 304 stainless steel overlay pipe weldments from the Hatch-2 BWR to determine the effectiveness of UT through overlays and the effects of the overlays on crack propagation in the weldments. Little correlation was observed between the results of earlier in-service ultrasonic inspection and the results of PT and destructive examination. Considerable difficult… more
Date: February 1, 1985
Creator: Park, J.Y.; Kupperman, D.S. & Shack, W.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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