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in subjects: "Valves"

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Reviews of ASME Section 11 pump and valve relief requests: Post Generic Letter 89-04

This paper presents a discussion of ASME Section 11 Pump and Valve Inservice Testing relief request reviews by the NRC and their contractors. Topics that will be discussed include the scope of USNRC reviews in Technical Evaluation Reports (TERs) (and Safety Evaluation, SEs); including the basis for granting relief requests, the status of relief requests in IST Program updates, and the Generic Letter 89-04 approval process; and the level of technical detail required in submitted programs. This p… more

Date: January 1, 1992

Creator: DiBiasio, A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Solar hot water system installed at Days Inn Motel, Jacksonville, Florida

The solar energy hot water system installed in the Days Inns of America, Inc., Days Inn Motel (120 rooms) I-95 and Cagle Road, Jacksonville, Florida, is described. The solar system was designed by ILI, Incorporated to provide 65 percent of the hot water demand. The system is one of eleven systems planned under this grant. Water (in the Solar Energy Products, Model CU-30ww liquid flat plate collector (900 square feet) system) automatically drains into the 1000 gallon lined and vented steel stora… more

Date: September 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Natural convection phenomena in a nuclear power plant during a postulated TMLB' accident

After the TMI (Three Mile Island) accident, there has been significant interest in analyzing and understanding the phenomena that may occur in a PWR (Pressurized Water Reactor) accident which may lead to partial or total core meltdown and degradation. Natural convection is one of the important phenomena. In the present paper the results of two numerical simulations of (1) four-loop PWR and (2) three-loop PWR are presented. The simulations were performed with the COMMIX(2) computer code. Our ana… more

Date: January 1, 1987

Creator: Domanus, H. M.; Schmitt, R. C.; Sha, W. T.; Shah, V. L. & Han, J. T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Uranium hexafluoride: Safe handling, processing, and transporting: Conference proceedings

This conference seeks to provide a forum for the exchange of information and ideas of the safety aspects and technical issue related to the handling of uranium hexafluoride. By allowing operators, engineers, scientists, managers, educators, and others to meet and share experiences of mutual concern, the conference is also intended to provide the participants with a more complete knowledge of technical and operational issues. The topics for the papers in the proceedings are widely varied and inc… more

Date: January 1, 1988

Creator: Strunk, W.D. & Thornton, S.G. (eds.)

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Kilowatt isotope power system. Component test procedure for the ground demonstration system radiator bypass valve

This test procedure provides a detailed description of the verification methods which shall be used in the developmental program to be conducted on the Kilowatt Isotope Power System (KIPS) Radiator Bypass Valve, to fulfill the requirements of the Ground Demonstration System Design Criteria. The test objective is to demonstrate the bypass flow characteristics of the valve as a function of the Jet Condensor Inlet Temperature. To accomplish the test objective the pump discharge temperature (TPO) w… more

Date: April 1, 1977

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Kilowatt Isotope Power System: component test procedure for the ground demonstration system flow control valve. 77-KIP-57

Test procedures to be used to demonstrate the temperature control function, flow control function, and transient response of the Mechanical Flow-Temperature Control Valve in the Kilowatt Isotope Power System are described in detail. (LCL)

Date: July 11, 1977

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Critical Technology List update. Final technical report

ICRC has reviewed and updated its List of critical technology. The List comprises all proposed SRC-I Demonstration Plant equipment whose use has been determined to involve some degree of potential safety, performance, or environmental risk. ICRC has subjected equipment on the Critical Technology c to special technical review to ensure the highest possible level of quality and lowest cost commensurate with acceptable overall risks. Equipment or equipment systems still considered to be high risk … more

Date: March 1, 1983

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Microwave measurement test results of circular waveguide components for electron cyclotron resonant heating (ECRH) of the Tandem Mirror Experiment-Upgrade (TMX-U)

Development of high-power components for electron cyclotron resonant heating (ECRH) applications requires extensive testing. In this paper we describe the high-power testing of various circular waveguide components designed for application on the Tandem Mirror Experiment-Upgrade (TMX-U). These include a 2.5-in. vacuum valve, polarizing reflectors, directional couplers, mode converters, and flexible waveguides. All of these components were tested to 200 kW power level with 40-ms pulses. Cold tes… more

Date: December 1, 1983

Creator: Williams, C.W.; Rubert, R.R.; Coffield, F.E.; Felker, B.; Stallard, B.W. & Taska, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Molten salt freeze seal. Final report

This report documents the results of the testing performed at Sandia National Laboratory, Albuquerque, New Mexico, on the applicability of a sodium freeze seal type valve stem in a molten salt environment. The freeze seal tests consisted of cycling the valve stem at set temperature intervals, checking the temperature distribution for freeze plug location, and verifying the actuator forces. In addition to the test results, this report also documents the engineering analysis and other tasks perfo… more

Date: August 1, 1985

Creator: Corugedo, J.J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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MHD air heater development technology. Progress report, November 26, 1979-March 31, 1980

Work on the development of the directly-fired high temperature air heater (HTAH) for MHD power plants is reported. Progress is reported on three tasks: (1) materials selection, evaluation, and development, (2) operability, performance, and materials testing, and (3) full-scale design concepts. Under Task 1, efforts were carried out in several areas. Work on the computer data base for material properties was begun. Data were compiled for several HTAH materials. Materials selections for Valve Tes… more

Date: May 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Is a 4-train support ''always'' more reliable than a 2-train support

Once the gross features of a frontline fluid system have been defined, one must consider what support system configuration will provide the best overall system performance. This paper considers different dc bus configurations for a given emergency feedwater system. Results indicate that a four-train support system (i.e., 4 dc buses) gives a lower system unavailability for transients, but a higher system unavailability for Anticipated Transients Without Scram (ATWS), than a two-train support sys… more

Date: June 1, 1986

Creator: Guey, C.N.; Arrieta, L. & Youngblood, R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Aging assessment of BWR control rod drive systems

This study examines the aging phenomena associated with boiling water reactor (BWR) control rod drive mechanisms (CRDMs) and assess the merits of various methods of managing this aging. Information for this study was acquired from (1) the results of a special CRDM aging questionnaire distributed to each US BWR utility, (2) a first-of-its-kind workshop held to discuss CRDM aging and maintenance concerns, (3) an analysis of Nuclear Plant Reliability Data System (NPRDS) failure cases attributed to… more

Date: January 1, 1991

Creator: Greene, R.H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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RF-GD/FTMS: An FTMS system with a lensless external ion source for high resolution elemental mass spectrometry

Two of the major challenges which face the field of elemental mass spectrometry are the development of versatile atomization/ionization sources for direct solids analysis and methods for reducing the impact of isobaric interferences found on commonly employed quadrupole and sector based instruments. The combination of radio frequency glow discharge (RF-GD) sources with Fourier transform ion cyclotron resonance mass spectrometry (FT-ICR or FTMS) is one technique which addresses both problems. A … more

Date: January 1, 1991

Creator: Weller, R. R.; Pochkowski, J. M.; Duckworth, D. C.; Marcus, R. K. & Buchanan, M. V.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Vacuum system transient simulator and its application to TFTR

The vacuum system transient simulator (VSTS) models transient gas transport throughout complex networks of ducts, valves, traps, vacuum pumps, and other related vacuum system components. VSTS is capable of treating gas models of up to 10 species, for all flow regimes from pure molecular to continuum. Viscous interactions between species are considered as well as non-uniform temperature of a system. Although this program was specifically developed for use on the Tokamak Fusion Test Reactor (TFTR… more

Date: January 1, 1977

Creator: Sredniawski, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Coal Technology Program. Progress report for December 1977

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: Report

Partner: UNT Libraries Government Documents Department

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Preliminary planning study for safety relief valve experiments in a Mark III BWR pressure suppression system

In response to a request from the Water Reactor Safety Research Division of the US NRC, a preliminary study is provided which identifies key features and consideration involved in planning a comprehensive in-plant Safety Relief Valve experimental program for a Mark III containment design. The report provides identification of program objectives, measurement system requirements, and some details quantifying expected system response. In addition, a preliminary test matrix is outlined which involv… more

Date: April 21, 1980

Creator: McCauley, E.W. & Holman, G.S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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TOPAZ - the transient one-dimensional pipe flow analyzer: user's manual

TOPAZ is a ''user friendly'' computer code for modeling the one-dimensional-transient physics of multi-species gas transfer in arbitrary arrangements of pipes, valves, vessels, and flow branches. This document serves as a user's manual for the code, and should provide potential users with enough information to take advantage of many of the code's capabilities. Details regarding equations and numerics, example problems, applications, and modeling assumptions will be discussed in companion docume… more

Date: July 1, 1985

Creator: Winters, W.S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Coal Technology Program progress report for August 1977

The projects reported this month include those for coal conversion process development, materials engineering, alkali metal vapor topping cycles, a coal equipment test facility, a fluidized bed combustor technology test unit, engineering and support studies, process and program assistance, and environmental assessment studies. In hydrocarbonization research, material balance results from Run HC-21 confirm earlier tests with Wyodak coal, showing an oil yield of 21% based on MAF coal. In the coal… more

Date: October 1, 1977

Item Type: Report

Partner: UNT Libraries Government Documents Department

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A tritium-compatible piezoelectric valve for the tokamak fusion test reactor

This work describes modifications made to a commercial piezoelectric valve to make it sufficiently tritium compatible for the TFTR trritium injection scenario. The results of testing the valve for leakage and performance following a series of progressively more severe tritium exposures are also presented. Finally, a proposal for a totally radiation-compatible piezoelectric valve, suitable for tritium-burning fusion machines of the future, is decribed. 9 refs., 2 figs., 1 tab.

Date: February 1, 1988

Creator: Coffin, D.O.; Cole, S.P. & Wilhelm, R.C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Main steam vent line piping and valve support reanalysis

A new support configuration for the one-inch Schedule 80 main steam vent line has been developed at the request of the LOFT Plant Systems Branch. This configuration will adequately support valves CV-P4-58 and CV-P4-59 without requiring supports at the centers of gravity of these valves as previously recommended. Dead weight, thermal expansion, seismic, LOCE and LOCA loading conditions were considered. Results indicate that the main steam vent piping will meet criteria specified in the ASME Code… more

Date: December 1, 1977

Creator: Nitzel, M.E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Aging assessment of Residual Heat Removal systems in Boiling Water Reactors

The effects of aging on Residual Heat Removal systems in Boiling Water Reactors have been studied as part of the Nuclear Plant Aging Research Program. The aging phenomena has been characterized by analyzing operating experience from various national data bases. In addition, actual plant data was obtained to supplement and validate the data base findings.

Date: January 1, 1992

Creator: Lofaro, R. J. & Aggarwal, S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Valve Applications at the SYNTHANE Plant in Mixed Phase Erosive Service

Three different control valves used for depressuring abrasive, high-pressure process streams containing coal fines have been improved by upgrading their trim materials. Original trims were of ceramic or of stainless steel coated with stellite; upgraded trims are tungsten carbide. The new materials have significantly improved valve life. These valves are in operation at the SYNTHANE Pilot Plant, a high BTU coal gasification facility operated for the Department of Energy by the Lummus Company. Th… more

Date: November 1, 1977

Creator: Bailey, Desmond M.; Massa, Adolph W.; Runnels, Oran D.; Strebinger, Peter C. & Lummus, C. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Summary of thermal-hydraulic calculations for a pressurized water reactor

The results of two transients involving the loss of a steam generator in a single-pass, steam generator, pressurized water reactor have been analyzed using a state-of-the-art, thermal-hydraulic computer code. Computed results include the formation of a steam bubble in the core while the pressurizer is solid. Calculations show that continued injection of high pressure water would have stopped the scenario. These are similar to the happenings at Three Mile Island.

Date: May 1, 1980

Creator: Bolstad, J.W. & Haarman, R.A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Ocean thermal energy conversion (OTEC) power system development (PSD) II. Preliminary design report. Appendix I: specifications and drawings

This volume contains the specifications and drawings prepared in support of the preliminary design of a 10MWe OTEC power system using enhanced plate type heat exchangers. Included are: (1) the specification tree; (2) system specification; (3) 10 MWe heat exchangers; (4) nitrogen storage, conditioning and supply subsystem specification; (5) ammonia storage, conditioning and supply specification; (6) electrical power distribution and control subsystem specification; (7) equipment valves, instrume… more

Date: August 10, 1979

Creator: Pearson, R.O.

Item Type: Report

Partner: UNT Libraries Government Documents Department