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Integrity of PWR pressure vessels during overcooling accidents

Description: The reactor pressure vessel in a pressurized water reactor is normally subjected to temperatures and pressures that preclude propagation of sharp, crack-like defects that might exist in the wall of the vessel. However, there is a class of postulated accidents, referred to as overcooling accidents, that can subject the pressure vessel to severe thermal shock while the pressure is substantial. As a result of such accidents vessels containing high concentrations of copper and nickel, which enhance… more
Date: January 1, 1982
Creator: Cheverton, R.D.; Iskander, S.K. & Whitman, G.D.
Partner: UNT Libraries Government Documents Department
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Coal Technology Program. Progress report for November 1977

Description: A block of Pittsburgh seam bituminous coal and a block of Wyodak subbituminous coal were pyrolyzed under reducing gas in support of in situ gasification. Information from previously completed block pyrolysis of bituminous coal under an argon atmosphere show that differences in evolved gas result from differences in heating rates. Compared to block pyrolysis at 0.3 C/sup 0//min, block pyrolysis at 3 C/sup 0//min produces less gas but gas with a higher heating value, yielding a higher overall pyr… more
Date: January 1, 1978
Partner: UNT Libraries Government Documents Department
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Metals and Ceramics Division. Annual progress report, ending June 30, 1980

Description: Research is reported concerning: (1) engineering materials, including materials compatibility, mechanical properties, nondestructive testing, pressure vessel technology, and welding and brazing; (2) fuels and processes consisting of ceramic technology, fuel cycle technology, fuels evaluation, fuel fabrication and metals processing; and (3) materials science which includes, ceramic studies, physical metallurgy properties, radiation effects and microstructural analysis, metastable and superconduc… more
Date: September 1, 1980
Partner: UNT Libraries Government Documents Department
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PNL technical review of pressurized thermal-shock issues. [PWR]

Description: Pacific Northwest Laboratory (PNL) was asked to develop and recommend a regulatory position that the Nuclear Regulatory Commission (NRC) should adopt regarding the ability of reactor pressure vessels to withstand the effects of pressurized thermal shock (PTS). Licensees of eight pressurized water reactors provided NRC with estimates of remaining effective full power years before corrective actions would be required to prevent an unsafe operating condition. PNL reviewed these responses and the r… more
Date: July 1, 1982
Creator: Pedersen, L. T.; Apley, W. J.; Bian, S. H.; Defferding, L. J.; Morgenstern, M. H.; Pelto, P. J. et al.
Partner: UNT Libraries Government Documents Department
open access

Effects of Seismic Vibrations on the Experimental Gas-Cooled Reactor

Description: The effects of seismic vibrations on the dynamic behavior of a composite system were analyzed. The equations of motion were derived and soIved with special emphasis on determining the resulting stresses. The method of analysis thus developed was applied to the composite structure consisting of the core, pressure vessel, and supporting skirt of the Experimental Gas-Cooled Reactor (EGCR). A system with three degrees of freedom was considered in order to determine the effects of an earthquake of t… more
Date: June 22, 1962
Creator: Witt, F.J.; Carver, D.R. & Maxwell, R.L.
Partner: UNT Libraries Government Documents Department
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Investigation of leaks in fiberglass-reinforced pressure vessels by direct observation of hollow fibers in glass cloth

Description: A simple method of visual observation of hollow fibers within fiberglass cloth has been developed. This visualization can aid in determining the contribution these fibers make toward leaks observed in fiberglass-reinforced epoxy resin pressure or vacuum vessels. Photographs and frequency data of these hollow fibers are provided. 3 figs.
Date: January 1, 1988
Creator: McAdams, J.
Partner: UNT Libraries Government Documents Department
open access

Static and dynamic analyses on the MFTF-B vacuum vessel. Revision 1

Description: The Mirror Fusion Test Facility is a major magnetic fusion energy project at the Lawrence Livermore National Laboratory. An important component of this facility is the vacuum vessel, which forms the vacuum chamber. The vessel is supported on twenty-two pairs of legs that rest on reinforced concrete piers. In performing static and dynamic analyses on the vacuum vessel, we separately investigated the load distribution under gravity loads, pressure loads, electromagnetic loads, and thermal loads. … more
Date: January 15, 1984
Creator: Ng, D.S.
Partner: UNT Libraries Government Documents Department
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Tests of Bearing Materials for the Experimental Through-Tubes in the Egcr

Description: The four experimental through-tubes provided in the Experimental Gas Cooled Reactor will extend directly through the core of the reactor and penetrate both the upper and lower pressure vessel heads. Each tube is anchored in an upper head nozzle and the bottom end is allowed to slide in a lower head nozzle. This lower nozzle is basically a T'' section that provides bottom access to the through-tube and a side access for the piping which connects the throughtube to the experimenter's cell. Due to… more
Date: July 16, 1962
Creator: MacPherson, R. E. & Smith, A. M.
Partner: UNT Libraries Government Documents Department
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A Theoretical Study of Destructive Nuclear Bursts in Fast Power Reactors

Description: The calculation of destructive nuclear bursts in fast reactors by an improved Bethe-Tait method, which, for purposes of calculation, neglects propagation of the pressure wave is described. TMen exact numerical calculations for hydrodynamic and neutronic conditions during the power burst are performed in order to assess the importance of this neglect. (auth)
Date: February 1, 1962
Creator: Jankus, V. Z.
Partner: UNT Libraries Government Documents Department
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SORPTION OF URANIUM ON ZIRCONIUM OXIDE

Description: The sorption of the ions of uranium, copper, and nickel on hydrous zirconium oxide was investigated at temperatures from 25 to 250 deg C. The experiments were performed by equilibrating 5 ml of the test solution with 0.5 g of zirconium oxide in a titanium autoclave, which was heated by means of a rocking furnace. The sorption of uranium was affected by characteristics of the zirconium oxide, temperatare of equilibration, and concentrations of uranium and of free acid in the uranyl sulfate solut… more
Date: September 13, 1961
Creator: Goldstein, G.
Partner: UNT Libraries Government Documents Department
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SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY

Description: A manual is given of the equipment and procedures used in the Army Reactor (SM-1A) to control the water purity and makeup. In addition to a description of the primary purification control system, a discussion is presented of the water chemistry control procedures for the auxiliary systems (e.g., the spent-fuel pit, the shield tank, and the waste disposal system). (T.F.H.)
Date: September 29, 1960
Creator: Chupak, J.
Partner: UNT Libraries Government Documents Department
open access

LWR-PV damage estimate methodology

Description: A credible estimate of the pressure vessel lifetime due to neutron-induced embrittlement is studied. The first step toward this goal is the accurate prediction of fluence and neutron energy spectrum at the pressure vessel. This, in turn, is obtained from least squares unfolding techniques of dosimetry measurements at a surveillance position, transport calculations, and a translation of information obtained at the surveillance position to the damage position. Including a prototypic neutron field… more
Date: January 1, 1980
Creator: Wagschal, J.J.; Maerker, R.E. & Broadhead, B.L.
Partner: UNT Libraries Government Documents Department
open access

ADVANCED PRESSURE VESSEL MATERIALS.

Description: Data on 5Cr - 3Mo - 12Ni alloy, PH13 - 8Mo and Iconel 718 for pressure vessel application are given. The 5Cr - 3Mo - 12Ni posseses characteristics suited to uniform aging of heavy sections. Tensile and toughness properties are good, and structural stability up to 315 deg C is adequate. Weldability with 12Ni - 3Cr - 3Mo filler material is good but 12Ni - 5Cr - 3Mo filler is more efficient. Aging characteristics of PH13 - 8Mo may not be suited to uniform aging of heavy sections. Excellent tensile… more
Date: October 31, 1969
Creator: Robertshaw, F.C.; Stephan, H.R. & McConnelee, J.E.
Partner: UNT Libraries Government Documents Department
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An Evaluation of Reactor Concepts for Use as Separate Steam Superheaters

Description: Various reactor concepts were compared for use as a separate superheater which could be added on to an advanced 300-Mwe reactor producing saturated steam. Fossil steam plant superheat temperatures were used as a criterion for selecting nuclear superheat temperatures. Therefore, the performance specified for the superheater was a minimum exit steam temperature of 566 deg C (1050 deg F) when supplied with saturated steam at either 7l atm (l050 psia) or l67 atm (2450 psia). A preliminary screening… more
Date: October 1, 1961
Creator: Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
Partner: UNT Libraries Government Documents Department
open access

Methods for measuring the surface tritium inside TFTR using beta decay

Description: Three potential methods for measuring the surface tritium content of the TFTR vacuum vessel are described, each based on a different technique for measuring the in situ beta emission from tritium. These methods should be able to provide both a local and a global assessment of the tritium content within the top [approx] 1[mu]m of the inner wall surface.
Date: January 1, 1994
Creator: Zweben, S. J.; Johnson, D. & Hill, K. (Princeton Univ., NJ (United States). Plasma Physics Lab.) (and others)
Partner: UNT Libraries Government Documents Department
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EBWR Reactor Pressure Vessel Revisions for Instrumentation and Increased Steam Output

Description: The procedures developed and utilized for the addition of connections to the EBWR pressure vessel after three yesrs of intermittent operation at the 20- Mw(t) design heat output are described. Major nozzle connections to the pressure vessel were made during two separated periods and under different conditions of vessel content. The details of the conversion sre discussed under the following topics: nozzle design, preparations, and nozzle installation. Diagrams and photographs are included. Radi… more
Date: January 1, 1962
Creator: Kettles, T.L. & Balai, N.
Partner: UNT Libraries Government Documents Department
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Quarterly Status Report on Ultra High Temperature Reactor Experiment (UHTREX) for Period Ending November 20, 1961

Description: The detailed design of the reactor proper was essentially completed and preparations were made for procurement of the carbon components and the pressure vessel. Design of the UHTREX facility has progressed to Titie lI. Design information is included on copper oxide beds and molecular sieves for gas cleanup. In other work, irradiation of capsules containing UHTREX fuel elements is reported along with fuel recycle research. (J.R.D.) 9578(Faye unscannable abstract)
Date: December 1, 1961
Partner: UNT Libraries Government Documents Department
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