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LEAKAGE OF WATER FROM GASKETED JOINTS PROPOSED FOR THE HWCTR. PART I

Description: When mockups of typical gasketed joints proposed for the HWCTR were subjected to thermal and pressure cycling that simulated reactor operating conditions, the average leakage rate was less than 0.11 lb of water per year per linear inch of gasket. The joints were exposed to deionized light water and were cycled 100 times from about 70 deg C and atmospheric pressure to 250 deg C and 1000 psig. (auth)
Date: July 1, 1960
Creator: Apple, F.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

105-KE Isolation Barrier Leak Rate Acceptance Test Report

Description: This Acceptance Test Report (ATR) contains the completed and signed Acceptance Procedure (ATP) for the 105-KE Isolations Barrier Leak Rate Test. The Test Engineer`s log, the completed sections of the ATP in the Appendix for Repeat Testing (Appendix K), the approved WHC J-7s (Appendix H), the data logger files (Appendices T and U), and the post test calibration checks (Appendix V) are included.
Date: June 14, 1995
Creator: McCracken, K. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NaK FREE CONVECTION COOLED SHAFT FREEZE SEAL FOR SRE PUMPS

Description: An investigation was conducted to determine the feasibility of using an NaK free-convection-cooled shaft freeze seal on the SRE main sodium pumps. The use of sodium in this application instead of tetralin eliminates the carburization hazard present should the seal coolant-(tetralin) leak into the sodium system. Results and recommendations are included. (J.R.D.)
Date: June 18, 1959
Creator: Perez, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Letter Report No. 14 Under AEC Contract AT(30-1)-2298

Description: Data for the rate of hydrogen permeation through nickel with 0, 2, and 4% copper added, at 640 to 800 deg C and 1.1.to 2 atm pressure are given. The system of nickel with 1% copper developed a high-temperature leak and had to be dismantled. Graphs plotted with this data are also included. (M.C.G.)
Date: June 1, 1960
Creator: Rudd, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Energy-efficiency design and inspection guides for affordable housing construction

Description: This paper focuses on the general methods used in guides developed for the energy efficient design and inspection of new and revitalized housing projects for military family housing. The methods and guides can also benefit the wider market of public and other housing. Inspections performed on military and public housing units were used to identify energy deficiencies. The most common problems found were related to disconnected and deteriorated forced air distribution duct work and poor system d… more
Date: December 1, 1997
Creator: Ternes, M. P.; Livengood, S. E. & Wendt, R. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Development of Convective Testing Methods for Low-Rise Multifamily Buildings. Final Report

Description: This report describes convective testing methods and protocols developed for use in weatherizing low-rise multifamily buildings. The methods can lead to controlling internal air movement and preventing leakage to the exterior by estimating magnitudes of air leakage pathways in garden and town house apartments. The 4 methods cited are: After-a-Retrofit; Equivalent Interfaces; Open-a-Door; and Add-a-Pathway. It is found that, because of modern interior finishing practices, convective problems ten… more
Date: August 1, 1996
Creator: Stiles, M.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An investigation of factors affecting the performance of laboratory fume hoods

Description: A `user tracer gas test` was performed on laboratory hoods, with a human subject standing in front of the hood, to assess hood containment ability. The relationship of face velocity and cross draft variables to hood containment ability is investigated. The ability of these variables and other tests, such as smoke challenges or tracer gas tests performed with a manikin at the hood, to predict the results of the user tracer gas test is evaluated. All of the laboratory hoods tested in this study w… more
Date: December 31, 1995
Creator: Altemose, B.A.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
open access

Analysis of NaOH releases for Hanford tank farms

Description: This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Caustic Spray Leak. The calculations needed to quantify the risk associated with this accident scenario are included within.
Date: July 25, 1996
Creator: Ryan, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Acceptance test procedure for the 105-KW isolation barrier leak rate

Description: This acceptance test procedure shall be used to: First establish a basin water loss rate prior to installation of the two isolation barriers between the main basin and the discharge chute in K-Basin West. Second, perform an acceptance test to verify an acceptable leakage rate through the barrier seals. This Acceptance Test Procedure (ATP) has been prepared in accordance with CM-6-1 EP 4.2, Standard Engineering Practices.
Date: May 19, 1995
Creator: McCracken, K. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interrupted pumpdown of a vacuum system

Description: The pressure rise due to a surface outgassing process following a real pump closure has been analyzed and found under a physically reasonable parameter selection to occur very quickly yet result in a very slight actual pressure change. Real leaks thus should be able to be able to be distinguished from surface outgassing processes by this technique.
Date: January 1, 1980
Creator: Edwards, D Jr
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

105 K East isolation barrier acceptance analysis report

Description: The objective of this document is to report and interpret the findings of the isolation barrier acceptance tests performed in 105KE/100K. The tests were performed in accordance with the test plan (McCracken 1995c) and acceptance test procedure (McCracken 1995a). The test report (McCracken 1995b) contains the test data. This document compares the test data (McCracken 1995b) against the criteria (McCracken 1995a, c). A discussion of the leak rate analytical characterization (Irwin 1995) describes… more
Date: May 31, 1995
Creator: McCracken, K. J. & Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Detecting leaks in hydrocarbon storage tanks using electrical resistance tomography

Description: Large volumes of hydrocarbons are stored worldwide in surface and underground tanks. It is well documented [1] that all too often these tanks are found to leak, resulting in not only a loss of stored inventory but, more importantly, contamination to soil and groundwater. Two field experiments are reported herein to evaluate the utility of electrical resistance tomography (ERT) for detecting and locating leaks as well as delineating any resulting plumes emanating from steel underground storage t… more
Date: April 3, 1995
Creator: Daily, W.; Ramirez, A.; LaBrecque, D. & Binley, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Testing of Containment Capabilities of Reinforced Concrete-Shielded Enclosures

Description: A reinforced concrete-shielded enclosure intended to contain nuclear reactor experiments was subjected to internal pressures up to 10 psig. The strains in reinforcing steel were measured with strain gages at critical locations for each pressure increment. These strains were compared with calculated strains; good agreement was found if the appropriate stress- concentration factors are applied at locations near re-entrant corners and wall openings. Leakagerate tests were performed to disclose the… more
Date: March 1, 1963
Creator: Fistedis, S.H.; Heineman, A.H. & Janicke, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hydrogen Distribution and Leak Rate From the Reactor Coolant System. Test Results, RNI-31 A. Core I, Seed 1

Description: No conclusions could be made concerning tbe distribution of hydrogen injected into the reactor coolant because the samples were taken only from the purification loop through which tae hydrogen was added. No comparison of the uniformity of distribution obtained by injecting hydrogen through either the AC or the BD purification loop could be made. Comparative data were not taken until 9 days had elapsed since injecting hydrogen and the concentration was near tbe lower limit (15 cc/kg). The rates … more
Date: June 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Monitoring the Cooling Air Effluent from the Brookhaven Graphite Research Reactor at the Point of Release and in the Environment

Description: The facilities for monitoring the particulate activity, Ar/sup 41/, and I/sup 131/ in the air effluent and the BGRR are described. The performance of the facilities under emergency conditions is studied for the release incident of Sept. 10 to 13, 1962; it is seen that the I/sup 131/ release, but not the particulate activity release, provided warning. (D.L.C.)
Date: January 1, 1963
Creator: Foelix, C. F. & Hull, A. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Periodic Reactor Plant Leak Rate Test. Core 1, Seed 2. Test Results T- 641102. First Issue, June 14, 1961

Description: Tests were performed on the Shippingport PWR to determine the magnitude and location of coolant system leakages. The total leakage from pressurizer relief and reactor relief valves was 62.1 gal/hr. The total plant leakage was 19.3 gal/hr. (T.F.H.)
Date: October 31, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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