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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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HIGH-TEMPERATURE IRRADIATION ON A ZIRCONIUM HYDRIDE-2 w/o URANIUM ALLOY

Description: Enriched ZrH/sub 1.65/ -2 wt.% uranium specimens were irradiated under 1 atm. of hydrogen at center-line temperatures between 900 to 1400 deg F to uranium burnups of between 13 and 25 at.%. Specially designed irradiation capsules were used to provide the conditions of temperature and hydrogen atmosphere which were required. Each capsule was instrumented with five thermocouples so that ample temperature data could be obtained during the irradiation. Almost negligible density changes were produce… more
Date: December 10, 1959
Creator: Lamale, Gerald E.; Hare, Alan W.; Krause, Horatio H.; Hopkins, Alan K.; Stang, John H.; Simons, Eugene M. et al.
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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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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Continuous Ion Exchange Development - A Qualitative Review

Description: Considerable interest has developed in the use of ion-exchange in the nuclear energy field in the last decade. Aside from the obvious use of providing demineralized coolant water for reactors, the projected uses of ion-exchange include the recovery of fission products from aquaeous waste streams and the separation and purification of fissionable materials from spent reactor fuels. The latter process may be incidental to the over-all operation, as is the case with the Purex anion exchange facili… more
Date: November 10, 1959
Creator: Nicholson, G. A.
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey. Section II. 4182-EFPH. Second Performance. Core I, Seed 1. Test Results DL-S-231 (T-612394)

Description: The purpose of the survey was to determine the radiation level in the Turbine Generator Services Building, around the Fuel Handling Canal, in the limited access areas of the reactor plant containers and on the boiler container roofs during plant operation. The test was performed with the plant at approximately 100 per cent power with three loops (1A, 1B, and 1C) in service. The radiation levels of the areas surveyed with a few exceptions were essentially background (.03 MR/HR). These exceptions… more
Date: November 10, 1959
Creator: Ritz, William C.
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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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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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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Unclassified Research and Development Programs Executed for the Division of Reactor Development and the Division of Research September 1959

Description: Basic Studies. It has been reported previously that a reduction of PuO2 to a suboxide does not occur when a powder sample is heated for one hour at 1450 C. To investigate this anomaly, the present hooded facilities were converted from full air flow to an argon atmosphere to prevent oxidation of a possible suboxide. Five grams of PuO2 powder were heated in dry hydrogen to 1500 C for times of one and eight hours. Immediately after discharge, they were mounted and transferred to a helium atmospher… more
Date: October 10, 1959
Creator: McEwen, L. H.
Partner: UNT Libraries Government Documents Department
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Energy Dissipation by Fast Electrons

Description: Report discussing the energy dissipated by fast electrons at different distances from monoenergetic electron sources, for plane perpendicular and point isotropic sources including tabulations and a summary of the theoretical methods and data utilized, and a table of spatial moments.
Date: September 10, 1959
Creator: Spencer, L. V.
Partner: UNT Libraries Government Documents Department
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Fretting Corrosion Irradiation Tests

Description: The Zircaloy-a clad, swaged UOa, 19-rod cluster fuel element for the PRTR was designed to use Zircaloy-a wire spirally wrapped around the fuel rods as spacing members. Such use of unbonded, Zircaloy-a spacers introduced the possibility of fretting corrosion. This paper reports preliminary irradiation tests conducted to determine whether or not such corrosions occurs in this fuel element design.
Date: September 10, 1959
Creator: Millhollen, M. K.
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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Quality Standards and Tests for Swaged Fuel Cladding

Description: The basic process for fabricating a swaged fuel rod is simple, easy to control and inexpensive. A zircaloy tube is filled with uranium dioxide powder, the ends temporarily plugged and the loaded tube is swaged to compact the UO2 powder to the required density. The swaged rod is then cut to length and counterbored and then end cape are welded into each end. After several tests and inspections, nineteen rods which meet the quality standards are assembled into a single fuel element ready for irra… more
Date: September 10, 1959
Creator: Olson, R. E.
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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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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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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SM-1 Research and Development Program, Activity Buildup Program Task 1 : final report February 1958 to June 1959

Description: Abstract: The results of activity buildup studies in the SM-1 (APPR-1) performed from February 1958 to January 1959 are reported. Data are presented on the extent, nature, and mechanism of the buildup of long-lived gamma emitting nuclides in the reactor primary system. Mathematical equations to describe the activity buildup are derived. Radiation levels after reactor shutdown are presented, as well as the predicted radiation levels at the end of core life.
Date: August 10, 1959
Creator: Brown, William S.; Bergen, C. Richard.; Bergmann, Carl A.; Chupak, Julius.; Fitzsimmons, Susanne R. & Grant, Louis G.
Partner: UNT Libraries Government Documents Department
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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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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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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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