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Symbols for Instrument Flowsheets and Drawings. A Recommended System for Application to ORNL Instrument Work

Description: Details concerning a recommended system of flow-plan symbols and drawings are given. The system is designed to identify the function of all major instrument components and to show schematically the operation of the instrument relative to the particular process. The system is used for identification and designation. (J.R.D.)
Date: June 19, 1962
Creator: Adams, R. K.; Davis, D. G.; Hyland, R. F. & Lieberman, B.
Partner: UNT Libraries Government Documents Department
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Boiling of Freon-114 in a Three-Foot Straight Tube Evaporator

Description: Introduction: this report covers two series of tests run on a Freon evaporator containing a vertical copper tube having an outside diameter of 7/8 of an inch, heated externally for a length of 35 inches by steam condensing in a concentric jacket.
Date: October 19, 1961
Creator: Allen, Charles F.
Partner: UNT Libraries Government Documents Department
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Vibrational Analysis of Unfired Horizontal Bayonet Tubes in a Fluidized Bed Calciner

Description: The heat exchanger of the calciner consists of a vessel into which unfired, horizontal, bayonet tubes extend in a fluidized bed. Strain measurements were taken on several of the tubes under simulated operating conditions and the associated dynamic stresses were calculated. Vibrations greater than design limitations for indefinite operation were found to exist. To restrict these vibrations and prevent further tube fatigue cracking, a tube support was installed. Since the installation of the support, the calciner has operated satisfactorily over 1275 hours. (auth)
Date: October 19, 1962
Creator: Anderson, S.D. & Hirschi, G.W.
Partner: UNT Libraries Government Documents Department
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͟v͟ic-Dioximes as Analytical Reagents

Description: This technical report discusses the synthesis of vic-dioximes, the analysis of vic-dioximes, the structure of vic-dioximes, the structure of metal(II)-vic-dioxime complexes, and analytical applications of this research. The report includes tables and figures that accompany the report's contents and findings.
Date: March 19, 1962
Creator: Banks, Charles V.
Partner: UNT Libraries Government Documents Department
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An Evaluation of the Uranium Contamination on the Surfaces of Alclad Uranium-Aluminum Alloy Research Reactor Fuel Plates

Description: Reported radioactivity in the Low-Intensity Test Reactor (LITR) water coolant traceable to uranium contamination on the surfaces of the alclad uranium-- aluminum plate-tyne fuel element led to an investigation to determine the sources of uranium contamination on the fuel plate surfaces. Two possible contributors to surface contamination are external sources such as rolling-mill equipment, the most obvious, and diffusion of uranium from the uranium-aluminum alloy fuel into the aluminum cladding. This diffusion is likely because of the 600 deg C heat treatments used in the conventional fabrication process. Uranium determinations based on neutron activation analysis of machined layers from fuel plate surfaces showed that rolling-mill equipment, contaminated with highly enriched uranium, was responsible for transferring as much as 180 ppm U to plate surfaces. By careful practice where cleanliness is emphasized, surface contamination can be reduced to 0.6 ppm U/sup 235/. The residue remaining on the plate surface may be accounted for by diffusion of uranium from the fuel alloy into and through the cladding of the fuel plate. Data obtained from preliminary diffusion studies permitted a good estimate to be made of the diffusion coefficient of uranium into aluminum at 600 deg C: 2.5 x 10/sup -8/ cm//sec. To minimize diffusion while the plate-type aluminum-base research reactor fuel element is being processed, heat treatments at 600 deg C should be limited to 2.5 hr. The uranium contamination on the surfaces of the finished fuel plates should then be less than 0.6 ppm U / sup 235/ . This investigation also revealed that the solubility limit of uranium in aluminum at 600 deg C is approx 60 ppm. (auth)
Date: March 19, 1962
Creator: Beaver, R. J.; Erwin, J. H. & Mateer, R. S.
Partner: UNT Libraries Government Documents Department
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Examination of a Nonregenerative Heat Exchanger From the u.s.s. Nautilus (Ssn-571)

Description: Selected components from a staianless steel nonregenerative heat exchanger removed from the U.S.S. Nautilus (SSN571) have been examined for evidence of stress-corrosion cracking. The examination was conducted on three baffle plates, all primary-face seal welds, and the tubes and the surrounding tube sheets of 7 out of a total of 35 tubes. Maximum operating temperature of the heat exchanger was 260 ction prod- F for the inlet primary water and 164 ction prod- F for the exit secondary water. Chloride content of the secondary water averaged 5 ppm, with a maximum of 15 ppm. Only one suspected stress-corrosion crack was found in the components normally in contact with the secondary water. The crack, 2.5 mils in depth, was located on a fully exposed tube. At the 95 per cent confidence level this represented a probability of finding cracking on fully exposed surfaces in 0 to 60 per cent of the rest of the tubes in the heat exchanger. Severe stress-corrosion cracking was found in tubes in the tube-sheet drain area at the juncture with the inner tube sheet at the inlet end, where secondary water seeped past the expanded tubes. Cracks were detected in five of seven tubes for a statistical probability of 25 to 96 per cent at the 95 per cent confidence level. Maximum depth of cracks was 28 mils or 80 per cent penetration of the 35-mil-thick tubing wall. Stress-corrosion cracks also were found around several holes on the drain-side tube-sheet surfaces at the inlet end. Maximum depth was 12 mils, which did not seriously threaten penetration of the 9/16-in.-thick tube sheet. Cracks were detected in 5 of 35 primary-face seal welds at the inlet end and in 11 of 35 at the outlet end. This behavior was attributed to hot-short cracking of the Type 347 stainless …
Date: February 19, 1960
Creator: Berry, W. E.; Stewart, O. M. & Fink, F. W.
Partner: UNT Libraries Government Documents Department
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Spectrophotometric studies of solutions at elevated temperatures and pressures: status and program for FY1961 and part of FY 1962

Description: A program was initiated on the spectrophotometric study of aqueous solution chemistry. The goal is operation at temperatures up to at least 330 deg C and at pressures up to 200 atm, and to near the critical point if this appears to be feasible. A spectrometer capable of operation under these extreme conditions is being designed. (W.L.H.)
Date: July 19, 1960
Creator: Biggers, R. E. & Chilton, J. M.
Partner: UNT Libraries Government Documents Department
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Thermal shield cooling tube surveillance: B, C, D, and K Reactors

Description: The top thermal shields of the Hanford reactors were formed by placing single layers of large cast iron blocks on the top of the graphite stacks. Accumulative distortion of the graphite stack is causing several inches of variation in the elevation of the originally level top thermal shields. The integrity of the top thermal shield cooling tubes is of concern because of the high axial and bending stresses they are subjected to from the shield variations in addition to the normal service conditions common also to the side and bottom thermal shields. Concern for possible deteriorating condition of the top cooling tubes has increased with the discovery of a leaking cooling tube at the C Reactor. This report provides information of the present condition of the cooling tubes and discusses continued surveillance of their condition which is required for evaluation of their continued serviceability.
Date: November 19, 1964
Creator: Bonham, C. E.
Partner: UNT Libraries Government Documents Department
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Status of Special Reactor Process Tube Loadings, July 1, 1965

Description: This report provides the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials.
Date: July 19, 1965
Creator: Bown, R. W.
Partner: UNT Libraries Government Documents Department
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A Precision Back-Reflection Laue Camera

Description: No Description Available.
Date: January 19, 1966
Creator: Brewer, A. W. & McDonald, R. R.
Partner: UNT Libraries Government Documents Department
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Judgment analysis of comparative C-64-F and X-8001-F alloy canned fuel element performance

Description: Fuel element component procurement requires a considerable lead time (three to four months after design is completed). Collection of data and statistical analyses to evaluate the performance of these components takes even longer. There is often reluctance to disturb the status quo in these matters without engineering recommendations; these are usually not given until the parameters are defined quantitatively with a high statistical level of significance. The purpose of this analysis is to take a qualitative look at material discharged to determine what conclusions can be drawn concerning the performance of C-64-F and X-8001-F clad fuel elements.
Date: April 19, 1960
Creator: Brown, R. W.
Partner: UNT Libraries Government Documents Department
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Measurement of Xenon Poisoning in the HRT

Description: Measurements obtained during three periods of HRT operations indicated that the xenon poison fraction was approximately 0.010. The technique used was based on mass spectrographic analyses of the stable xenon isotopes in the reactor off-gas stream. Models proposed to explain the measurements show that xenon, which is formed primarily by decay of iodine adsorbed on the pipe walls, is held up on the walls, out of the circulating stream, for an average period of about eight hours. (auth)
Date: April 19, 1962
Creator: Burch, W.D.
Partner: UNT Libraries Government Documents Department
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Feasibility Study of a New Mass Flow System : Quarterly Report No. 2 Covering the Period from September 1 to November 30, 1960

Description: This is the second quarterly report that documents a system of mass flow that can record measurements of homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, additionally considering pressure drops, measuring external to the flow, ruggedness and reliability.
Date: December 19, 1960
Creator: Burgwald, G. M.; Stone, C. A. & Genthe, William K.
Partner: UNT Libraries Government Documents Department
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FEASIBILITY STUDY OF A NEW MASS FLOW SYSTEM. Quarterly Report No. 2 Covering the Period from September 1 to November 30, 1960

Description: Activities in a development program for a mass flow system capable of measuring homogeneous flow, slurries, highly corrosive fluids, and multiphase fluids are reported. The first experimental mass flow meter is nearly complete, and the required intensity of the radioactive source for mass measurements is being determined. Design of the vibrating reeds for the sources are completed. Absorption measurements at energies <100 kev indicate that composition effects are present, however, the effect is not considered serious since the system can be calibrated for each particular material. (J.R.D.)
Date: December 19, 1960
Creator: Burgwald, G.M.
Partner: UNT Libraries Government Documents Department
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