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High Pressure Low Resistance Joint

Description: The following report describes the usage of tin-foil to obtain a mechanical joint of low electrical resistance while providing a seal to hold water at a pressure of 300 psi.
Date: March 28, 1955
Creator: Peters, Ralph
Partner: UNT Libraries Government Documents Department

REDUCING ULTRA-CLEAN TRANSPORTATION FUEL COSTS WITH HYMELT HYDROGEN

Description: This report describes activities for the seventh quarter of work performed under this agreement. We successfully completed atmospheric testing in the previous quarter. We await approval from the Swedish pressure vessel board to allow us to proceed with the procurement of the vessel for super atmospheric testing.
Date: July 1, 2004
Creator: Malone, Donald P. & Renner, William R.
Partner: UNT Libraries Government Documents Department

REDUCING ULTRA-CLEAN TRANSPORTATION FUEL COSTS WITH HYMELT{reg_sign} HYDROGEN

Description: This report describes activities for the eighth quarter of work performed under this agreement. We await approval from the Swedish pressure vessel board to allow us to proceed with the procurement of the vessel for super atmospheric testing.
Date: April 1, 2005
Creator: Malone, Donald P. & Renner, William R.
Partner: UNT Libraries Government Documents Department

REACTOR CONTAINMENT (INCLUDING A TECHNICAL PROGRESS REVIEW)

Description: An attempt is made to present available information pentinent to reactor containment. This is done directly, by summary and reference, or by reference alone. To provide a reference framework, the first review document must necessarily be handled differently from supplemental periodic reviews. The plan is to: (3) provide a detailed account of the problem and suggestions for work needed to yield adequate solutions; (2) present the accumulated knowledge and accomplishments; (3) give an account of experience in applying the containment concept; and (4) append extensive bibliographical material. An attempt is made in each case to indicate the significance of the information and its relation to the problems outlined. (A.C.)
Date: May 1, 1959
Creator: Brittan, R.O.
Partner: UNT Libraries Government Documents Department

Reducing Ultra-Clean Transportation Fuel Costs with HyMelt Hydrogen

Description: This report describes activities for the fifteenth quarter of work performed under this agreement. MEFOS, the gasification testing subcontractor, reported to EnviRes that the vendor for the pressure vessel for above atmospheric testing plans to deliver it by October 20, 2006. MEFOS performed a hazardous operation review of pressurized testing.
Date: July 1, 2006
Creator: Malone, Donald P. & Renner, William R.
Partner: UNT Libraries Government Documents Department

Pressure Vessel Steel Surveillance Program for General Electric Power Reactors

Description: Abstract: "Pressure vessel steel surveillance programs are performed in nuclear power reactors to provide knowledge of the mechanical properties of the pressure vessel material as neutron irradiation proceeds. A standard surveillance program is described. Design of specimens, capsules, and associated equipment, as well as selection of test material and techniques for special preparation and testing, are discussed."
Date: January 8, 1965
Creator: Brandt, F. A.
Partner: UNT Libraries Government Documents Department

Rupture Hazard of Pressure Vessels

Description: A report about the hazards of maintaining pressure vessels. Improperly operated pressure vessels can kill and injure workers and others, and cause extensive damage even if the contents are benign.
Date: May 1997
Creator: United States. Environmental Protection Agency.
Partner: UNT Libraries Government Documents Department

PHOTOELASTIC STUDY OF STRESS IN PERFORATED HEMISPHERICAL CLOSURES FOR A PRESSURE VESSEL. Research Report 100FF996-R1

Description: Photoelastic ''frozen stress'' tests were made of perforated hemispherical closures for a pressure vessel. Three different hole patterns were investigated. The ''circular'' and ''square'' arrangements of holes showed the highest peak stress, a value of stress + pressure of about 10 being noted in each. In comparison, the ''triangular'' arrangement of holes yielded a peak value of 8.20. (auth)
Date: January 1, 1957
Creator: Sampson, R.C. & Leven, M.M.
Partner: UNT Libraries Government Documents Department

ASME code ductile failure criteria for impulsively loaded pressure vessels

Description: Ductile failure criteria suitable for application to impulsively loaded high pressure vessels that are designed to the rules of the ASME Code Section VI11 Division 3 are described and justified. The criteria are based upon prevention of load instability and the associated global failure mechanisms, and on protection against progressive distortion for multiple-use vessels. The criteria are demonstrated by the design and analysis of vessels that contain high explosive charges.
Date: January 1, 2003
Creator: Nickell, Robert E.; Duffey, T. A. (Thomas A.) & Rodriguez, E. A. (Edward A.)
Partner: UNT Libraries Government Documents Department

Critical Soil-Structure Interaction Analysis Considerations for Seismic Qualification of Safety Equipment

Description: While developing seismic analysis models for buildings that support safety-related equipment, a number of issues should be considered to ensure that the input motions for performing seismic qualification of safety-related equipment are properly defined. These considerations are listed and discussed here with special attention to the effect and importance of the interaction among the foundation soil, the building structure, the equipment anchors, and the equipment structure. Typical industry practices are critically examined to assess their adequacy for determining the input motions for equipment seismic qualification. The features that are considered essential in a soil-structure interaction (SSI) model are described. Also, the effects of inappropriate treatment or representation of these features are discussed.
Date: March 4, 2004
Creator: Hossain, Q A
Partner: UNT Libraries Government Documents Department

Reactor Flow Studies : Full Scale Model Flow Tests

Description: From foreword: This report contains the test results and analysis of test results of flow studies and reactor vessel internals. Tests were performed at, below, and above the PM-1 design flow rate to observe flow distribution and pressure drops within the reactor vessel, as well as the overall reactor vessel pressure drop.
Date: June 1961
Creator: Taylor, W. J.; Starr, I. & Baer, R. L.
Partner: UNT Libraries Government Documents Department