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Steady State Thermal Behavior of Hnpf Sodium Heat Transfer System

Description: The performance of the Hallam Nuclear Power Facility heat transfer components was investigated in order to determine the steady-state, part load characteristics under various operating conditions. The complete steady-state temperature distributions, variations of flow rates and heat transfer coefficients throughout the sodium heat transfer systems as functions of reactor load are shown in a series of graphs. (M.C.G.)
Date: August 10, 1959
Creator: Stell, A.T.
Partner: UNT Libraries Government Documents Department
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NUCLEAR PROPERTIES OF ANTINUCLEONS

Description: No Description Available.
Date: December 10, 1959
Creator: Segre, Emilio
Partner: UNT Libraries Government Documents Department
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Investigation of Graphite Bodies : Progress Report No. 3 for the Period March 1, 1959 to May 31, 1959

Description: This document is the third in a series of progress report that records investigations of graphite bodies. Along with the report, two appendices are given to describe the different graphite bodies: "Synthetic Binders for Carbon and Graphite" and "High Temperature Physical Properties of Molded Graphites".
Date: June 10, 1959
Creator: Bradstreet, Samuel W.
Partner: UNT Libraries Government Documents Department
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PT-IP-280-A-FP, irradiation of alloyed dingot uranium fuel elements

Description: The objective of this test is to authorize irradiation of pilot quantities of alloyed dingot uranium and to provide for monitoring of its performance. This test will authorize: (a) Charging of up to 50 tons of alloyed dingot fuel elements in two groups of 25 tons each, including 12 monitor charges which will accompany the first group, into D Reactor as a pilot loading. Although purer and ore dense than standard ingot uranium, the dingot uranium produced in the past by MCW has demonstrated poore… more
Date: October 10, 1959
Creator: Hall, R. E.
Partner: UNT Libraries Government Documents Department
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Production test IP-296-D, swelling test of natural and three percent enriched metallic uranium

Description: The objective of this production test authorization is to permit the irradiation of sixteen, 0.394 inch diameter, metallic uranium spheres at temperatures between 300C and 800C in the 3674 ank 3865 KW front-to-rear test tubes. Eight spheres will be of natural uranium and eight of enriched (3% U-235) uranium. Temperature controlled and temperature monitored test capsules containing either four natural or three percent enriched uranium spheres will be irradiated. Pre- and post -irradiation examin… more
Date: December 10, 1959
Creator: Marshall, R. K.
Partner: UNT Libraries Government Documents Department
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Evaluation of NaK as the Primary Coolant for the SNAP II System

Description: An evaluation was made of the use of NaK as the primary coolant for the SNAP-2 system. Pumping-power limitations based on the mercury Rankine cycle are analyzed. Problems pertinent to any design-specification modifications are reviewed.
Date: July 10, 1959
Creator: Wallerstedt, R.
Partner: UNT Libraries Government Documents Department
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Surface Motions from a Series of Underground Nuclear Tests

Description: Abstract: Ground effects resulting from Blanca, Logan, Evans, Tamalpais and Mars events of HARDTACK Phase II underground explosions were measured by strong-motion and teleseismic seismographs out to distances of nearly 100 miles.
Date: August 10, 1959
Creator: Carder, D. S.; Cloud, W. K.; Pearce, T. H. & Murphy, L. M.
Partner: UNT Libraries Government Documents Department
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Determination of fuel element warp and hot spot orientation

Description: The angular relationships of warp to rib marks and warp to hot spots were measured for a large number of fuel elements. The data was analyzed and found to provide information regarding the formation of warp and hot spots.
Date: June 10, 1959
Creator: Deobald, T. L.
Partner: UNT Libraries Government Documents Department
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The Palmolive cycle at Hanford

Description: The Palmolive program is directed toward the recovery of neptunium-237 and production of plutonium-238. The neptunium is recovered during the chemical processing of irradiated uranium and is purified and fabricated into target elements. The target elements are irradiated to produce plutonium-238 by neutron capture of neptunium-237 and are processed to provide plutonium for shipment to the final customer and neptunium for recycle within the system. This report summarizes a preliminary engineerin… more
Date: July 10, 1959
Creator: Beard, S. J. & Judson, B. F.
Partner: UNT Libraries Government Documents Department
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Report on preliminary laboratory experiments investigating consequences of failure of front hydraulic fittings in K reactor geometry

Description: The purpose of this report is to present the results of a brief series of transient heat transfer experiments directed toward determining the possibility of damage to a K reactor should a front hydraulic connector fail to a tube containing I&E fuel elements. Nuclear heating of a train of 32 I&E slugs was simulated by electrically heating a rod in a K geometry process tube. Failure of a front fitting to such a tube was simulated by simultaneously and rapidly closing a valve in the water supply t… more
Date: September 10, 1959
Creator: Hesson, G. M. & Fitzsimmons, D. E.
Partner: UNT Libraries Government Documents Department
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Survey of PWR Power Plants, 10-30 eMW Size

Description: Foreword: In early 1959 the U.S. Atomic Energy Commission initiated a study to assess the feasibility of low-level power generation through the use of certain types of small-sized nuclear reactors.
Date: October 10, 1959
Partner: UNT Libraries Government Documents Department
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ORR OPERATIONS FOR PERIOD APRIL 1958 TO APRIL 1959

Description: It has been the custom to report the operating experience at the ORR along with other activities in the reports of the ORNL Operations Division. It was decided to combine the sections of the Operations Division reports appropriate to ORR operation covering the year from April 1958 through March 1959. (W.D.M)
Date: September 10, 1959
Creator: Cox, J.A.
Partner: UNT Libraries Government Documents Department
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SOLIDS ACCUMULATION AND FISSION HEATING IN THE HRT CHEMICAL PLANT UNDERFLOW POT (CO-OP REPORT, FALL QUARTER, 1958)

Description: A study was conducted to develop equations for calculating fission product heating in the RRT-CP undeflow pot from measured temperatures and to attempt to correlate the rate of solids accumulation in the undeflow pot with flssion heating and reactor power. Using fission heating data calculated from the heat balances developed, several semi-empirical equations relating solids accumulation and heating were tested. In one case an error of no greater thaQ 26% was incurred in the calculation of the … more
Date: June 10, 1959
Creator: Dunn, W E
Partner: UNT Libraries Government Documents Department
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BASIC PRINCIPLES OF SCINTILLATION COUNTING

Description: The basic principles of scintillation counting are reviewed. The design, performance, and operation of a placed on instruments ior medical uses. (C.H.)
Date: December 10, 1959
Creator: Harris, C.C.; Hamblen, D.P. & Francis, J.E.
Partner: UNT Libraries Government Documents Department
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A BOILING WATER ANALYSIS CODE ON THE IBM-650--ABWAC-MNC PROGRAM NO. 302

Description: A method was developed for using an IBM-650 data processing machine to obtain detailed information concerning thermal and hydraulic conditions within a platetype reactor channel when the coolant in the channel is present in both vapor and liquid phases. (auth)
Date: March 10, 1959
Creator: Beretsky, I. & Pacine, S.
Partner: UNT Libraries Government Documents Department
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Study of Factors Influencing Ductility of Iron-Aluminum Alloys. Monthly Letter Report No. 7

Description: The objective of the program is to determine the effect of variations of Al content, heat treatment, and basic slip mechanism upon the room temperature ductility of Fe - Al alloys. Additional heat treatment studies on 13.9 Alfenol tends to confirm earlier observations that reproducibility of ductility values of 8 to 9% are difficult to obtain. The preparation of Al - Y - Fe, and Al - Mo - Y - Fe alloys by arc melting in a non-consumable electrode arc furnace is reported. A resistivity versus te… more
Date: November 10, 1959
Creator: Perkins, F. C. & Nachman, J. F.
Partner: UNT Libraries Government Documents Department
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Boundary-layer formation in the pinch

Description: From abstract: "A study is made of various processes that occur prior to the pinch effect when an electric field is applied to a deuterium gas. The variables of the problem are percentage of ionization, the electron and ion temperatures, the resistivity of the gas, and the current density."
Date: August 10, 1959
Creator: Killeen, John; Gibson, Gordon & Colgate, Stirling A.
Partner: UNT Libraries Government Documents Department
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Determination of Li6 in Aqueous Solution by Neutron Activation Analysis

Description: A method for determining the concentration of Li6 in aqueous solution has been tested using the nuclear reactions Li6 (n,α)H3 and O16 (H3,n)F18. Annihilation 7 radiation of induced 1.87 hour F18 radioactivity was counted with a well-type scintillation counter, and the radioactivity per millimole of lithium was found to be independent of lithium concentration below about 0.2moles/liter. The sensitivity limit for detecting lithium is less than 0.1 micromole (0.0075 micromole Li6).
Date: July 10, 1959
Creator: Winchester, J. W. & Bate, L. C.
Partner: UNT Libraries Government Documents Department
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Thermodynamic and Transport Properties of Gaseous Carbon Dioxide

Description: The thermodvnamic and transport properties of gaseous CO/sub 2/ are presented. The properties were coruputed from the most recent data. The results are presented graphically with pressure and temperature as independent variables for convenience in engineering calculations. (J.R.D.)
Date: August 10, 1959
Creator: Chen, L. H.
Partner: UNT Libraries Government Documents Department
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PLUTONIUM GRAPHITE ASSEMBLIES--PART II

Description: Neutron multiplication measurements were made on a number of cylindrical assemblies of Pu and graphite disks. S/sub n/ calculations were made on homogeneous mixtures of Pu and graphite with varying C/Pu ratios and varying reflector thickness. (auth)
Date: August 10, 1959
Creator: Goodwin, A. Jr. & Schuske, C.L.
Partner: UNT Libraries Government Documents Department
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A Theoretical and Experimental Investigation of the Temperature Response of Pig Skin Exposed to Thermal Radiation

Description: Estimates indicate that first degree burns on the bare skin will be sustained 30 miles from a 10 megaton nuclear blast. Results are reported from a theoretical and experimental investigation of the temperature response of pig skin exposed to thermal radiation. While the study deals with radiant energy heating of skin, it is concluded that results may be applied to other modes of energy input. Methods were developed for the comparison of theoretical predictions with experimental results. An atte… more
Date: June 10, 1959
Creator: Davis, T. P.
Partner: UNT Libraries Government Documents Department
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