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105-N charge-discharge rates

Description: Figures have and can be generated that indicate a higher charge-discharge rate if required before 105-N will be comparable with existing reactors. Also, these figures show an apparent operating cost incentive to increase the charge-discharge rates proposed for 105-N. Although these figures may be true by themselves, other figures developed from the same information and stated on a basis that affords a true comparison, show that the proposed rates for 105-N are compatible with those in existing … more
Date: July 2, 1959
Creator: Nesbitt, J. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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190-C pump capacity

Description: The purpose of this document is to update 190-C pump capacity information previous released in HW-52449{sup 1} and HW-58580{sup 2}. Improvements in motor cooling has resulted in raising the previous 3500 HP limit to 3660 HP{sup 3} thus increasing total pumping capacity.
Date: June 22, 1959
Creator: Watson, D. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Activation Analysis Nuclear Chemical Research Radiochemical Separations. Progress Report No. 8 for November 1958-October 1959

Description: Activities at the Michigan Reactor and pneumatic tube system are outlined. Various modifications including installation and operation of a "bunny" rabbit pneumatic tube system for transferring samples from laboratory to counter are described. Prelimirary investigation for design of a neutron generator for activation work is described. Modifications to the 100-channel pulse-height analyzer including addition of auxillary circuits and additioral detectors are sumnnarized. In nuclear chemistry a c… more
Date: November 1, 1959
Creator: Maddock, R. S. & Meinke, W. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Adsorption of Xenon in an Activated Charcoal Column

Description: Performance characteristics of two activated charcoal columns at room temperature in separating fission-product xenon from an air stream were investigated by installing each column in the exhaust from an enclosure in which irradiated slugs were dissolved. Breakthrough curves are presented and the variation in xenon concentration within the columns is examined. Theoretical treatments of adsorption columns in the literature are found to agree well with the experimental data. Performance of the co… more
Date: May 11, 1959
Creator: Cantelow, H. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ADVANCED DESIGNS OF MAGNETIC JACK-TYPE CONTROL ROD DRIVE

Description: The magnetic jack is a device for positioning the control rods In a nuclear reactor, especially in a reactor containing water under pressure. Magnetic actuation precludes the need for shaft seals and eliminates the problems associated with mechanisms operating in water. It consists of a pressure shell, four sets of external stationary magnet coils (hold, grip, lift, pull down), and one Internal moving part (ammature) that impants linear motion to a cluster of rods. (W.L.H.)
Date: November 1, 1959
Creator: Young, J.N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advantages of palmolive alternate

Description: It has been proposed that Pu-238 be produced by irradiating neptunium solution in one or more loops in a reactor and then recovering the Pu-238 in a close-coupled separations plant. Such a scheme could replace the more conventional scheme of solid element fabrication, irradiation, and reprocessing for plutonium and neptunium recovery. This document presents the advantages of such a scheme from the standpoint of product purity and Pu-238 production.
Date: March 17, 1959
Creator: Coppinger, E. A. & Merrill, E. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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AETR NUCLEAR MOCKUP DESIGN

Description: The Advanced Engineering Test Reactor (AETR) nuclear mockup is designed to be a flexible, inexpensive developmental facility which duplicates the reactor portion of the AETR and which would be used to verify the operation of reactor controls. The mockup would also furnish measurements of temperature and void coefficients, flux shapes, and critical mass, and facilitate a reliable AETR design in a minimum time, and with minimum development cost. For even greater usefulness, the mockup is also des… more
Date: October 1, 1959
Creator: Leonard, B.H.; Bertelson, P.C.; Kornfeld, M.J. & Wade, E.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Agglomeration of Solid Aerosol Particles. Technical Report No. 16

Description: The variations of size and density of aerosol particles were examined. Experiments were made with a wide variety of substances using a modification of Whytlaw-Gray and Patterson's methods in which freefall velocity was determined. The mass was estimated both by balancing the gravitational and electrostatic forces and from rising velocities under constant field strength. The results were compared with the shape and structure of the aerosols shown by electron microscopy. The variation of the Stok… more
Date: March 1, 1959
Creator: Johnstone, H. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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AIR CORE CRYOGENIC MAGNET COILS FOR FUSION RESEARCH AND HIGH ENERGY NUCLEAR PHYSICIS APPLICATIONS

Description: It is shown that cryogenic techniques offer the possibility of substantially improving the efficiency and practicality of generating high magnetic fields in air-core coils of large size. Over-all reductions in power requirements of as high as 25, by comparison with conventional coils, are predicted, provided high purity conductors and efficient refrigeration cycles are used. (W.D.M.)
Date: October 30, 1959
Creator: Post, R. F. & Taylor, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LOS ALAMOS MOLTEN PLUTONIUM REACTOR EXPERIMENT (LAMPRE) HAZARD REPORT

Description: This report supersedes K-1-3425 and LA-2327(Prelim). The first experiment (LAMPRE I) in a program to develop molten plutonium fuels for fast reactors is described and the hazards associated with reactor operation are discussed and evaluated. The reactor desc=iption includes fuel element design, core configuration, sodium coolant system control, safety systems, fuel capsule charger, cover gas system, and shielding. Information of the site comprises population in surrounding areas, meteorological… more
Date: June 1, 1959
Creator: Swickard, E. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ALUMINA-CLAD UO$sub 2$ FOR FUEL APPLICATIONS

Description: Using a special reactive form of high-purity alumina, claddings were applied to UO/sub 2/ particles by a tumbling technique. The clad pellets were isostatically pressed at 100,000 psi and then sintered at 2800 deg F in hydrogen. crack-free spheroidal pellets ranging from 1000 to 2000 mu in diameter were produced. The dense Al/sub 2/O/sub 3/ envelopes surrounding the UO/sub 2/ particles were estimated to be 300 to 500 mu thick. The Al/sub 2/O/sub 3/ claddings protected the UO/sub 2/ from oxidati… more
Date: February 18, 1959
Creator: Smalley, A.K.; Riley, W.C. & Duckworth, W.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of 100-K emergency water requirements after CGI-844 pump failure

Description: The demand plot has a 5-set, modified pump decay curve; it shows that 20,000 gpm emergency flow would be required within 80 seconds of complete pump power failure. Bases for the demand curve are constant bulk inlet temperature of 2 C, constant bulk outlet temperature of 95 C, K-3 I&E fuel elements, and initial reactor flow of 188,000 gpm.
Date: May 28, 1959
Creator: Corlett, R. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of data from IP-56-A-86MT: Evaluation of dimensional stability characteristics of low hydrogen uranium I and E fuel elements

Description: This production test was designed to evaluate the suitability of low hydrogen dingot uranium as routine process material. Nine tubes of I and E fuel elements (6 dingot, 3 ingot) with 32 fuel elements in each tube, have recently been discharged at the C Reactor and this document contains the results of analyses made on the dimensional stability properties of this material.
Date: April 9, 1959
Creator: Stewart, K. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Fuel Element Core Blanks for Argonne Low Power Reactor by Gamma Counting

Description: A technique based on a determinaiion of the differential counting rate exhibited by the 184-kev gamma radiation associated with the decay of U/sup 235/ was developed for the determination of the U/sup 235/ content in Argonne Low Power Reactor fuel element core blanks. The Argonne Low Power Reactor core blanks were an aluminum-highly enriched uranium alloy containing 17.5 weight per cent uranium (approximately 4 g U/sup 235/) having the following dimensions: length, 6.875 inches, width, 3.31 inc… more
Date: December 1, 1959
Creator: McGonnagle, W. J. & Perry, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ANALYSIS OF NEUTRON PULSES IN A GODIVA-TYPE REACTOR

Description: Some calculations have been made to estimate the characteristics of a neutron-burst type fast reactor similar to Godiva but made up of relatively small component parts--the so-called "layered assembly." One spherical and three cylindrical assemblies have been considered. Critical masses, assuming 5% voids, range from 58 to 65 kg of 93.4% enriched U/sup 235/. For a reactivity addition of 0.33 dollars above prompt criticals bursts between 2 x 10/sup 17/ and 6.7 x 10/ sup 17/ fissions were compute… more
Date: February 25, 1959
Creator: Nestor, C.W. & Tobias, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Radiation From Hnpf Cold Traps and Primary Sodium Pumps During Removal and Shipping

Description: The expected maximum contamination of the HNPF cold traps and primary sodium pumps was determined along with the maximum dose rates from these components during removal and shipping. Suitable shielding for casks to be used in the removal operation and for shipping these components away from the reactor site is specified. Access to an unshielded cold trap is limited by high dose rates, i.e., 100 mr/hr at 120 ft, after 180 days decay time. A handling cask providing a radial shield of 3 in. of lea… more
Date: December 15, 1959
Creator: Rhoades, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE ANALYSIS OF REFRACTORY BORIDES, CARBIDES, NITRIDES, AND SILICIDES

Description: Methods are presented for the analysis of 41 refractory materials. An evaluation of the accuracy and the precision of these techniques are also given The materials studied are the borides of hafnium, molybdenum, niobiumL rhenium, tantalum, thorium, titanium, tungsten, uranium vanadium, and zirconium; the carbides of hafnium molybdenum, miobium, silicon, tantalum, thorium, titanium, tungsten, uranium, vanadium, and zircomium; the nitrides of boron, hafnium, niobium, silicon, tantalum, titanium, … more
Date: March 1, 1959
Creator: Kriege, O.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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