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An Improved Nuclear Measuring Principle : Quarterly Progress Report No. 3 Covering the Period from December 1, 1959 to March 1, 1960

Description: This report is the third in a series of quarterly reports discussing the concept and progression of an improved method in nuclear measuring than the usage of the scintillation counter. This report indicates that in a chopped double beam system, commutation of the detector current permits selection of optimum response time and size of radioactive sources.
Date: March 28, 1960
Creator: Burgwald, G. M. & Stone, C. A.
Partner: UNT Libraries Government Documents Department
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Evaluation and Design Heavy Water Moderated Power Reactor Plants

Description: From introduction: This report has been prepared to present the details of the heavy water cooled power reactors, including cost estimates, plant design studies, and other work directly related to the current status of D2O reactors.
Date: April 28, 1960
Partner: UNT Libraries Government Documents Department
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Reactivity Absorbed by Xenon-135 in the SRE

Description: Abstract: The measurement and calculation of the reactivity absorbed by Xe135 as functions of time after shutdown for the SRE are described.
Date: January 28, 1960
Creator: Woodruff, R. W.
Partner: UNT Libraries Government Documents Department
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Expansion to 4.0 capacity factor: Purex Engineering Study

Description: The Purex Plant was originally designed to operate at a instantaneous rate of 8-1/3 tons of uranium per 24-hour day on a three-cycle flowsheet. Subsequently, the rate was increased to 26-2/3 T/day and the process changed to a two-cycle flowsheet. Recently, flowsheet changes made for neptunium recovery and replacements of certain critical equipment items have altered the plant`s capacity. The status of the plant is discussed in the Continuity of Operations, Plant Improvement Program, Reference 1… more
Date: October 28, 1960
Creator: Doud, E.
Partner: UNT Libraries Government Documents Department
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Resume of KER Loop irradiation tests for 1957, 1958, and 1959

Description: In 1957 three of the four high temperature recirculating loops in KE Reactor were put into service and in 1958 the fourth loop was started up. The primary purpose of the loops has been high temperature irradiation testing of fuel elements in support of the NPR fuel element development program, although tests have been run to provide information for PRTR fuel development and high temperature aluminum corrosion programs. Coolant technology studies relating to activity build-up, crude formation, c… more
Date: March 28, 1960
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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KER-1 thermal cycle

Description: Enclosed is the data that was collected during the recent thermal cycle of KER-1. This data includes the RTD readings and information taken from the thermocouple fuel element. In conjunction with obtaining data on film build-up, the test provided an excellent opportunity to study the effect of temperature on measured tube power. It has been noticed that the KER reactor tubes appear to produce more power (greater {Delta}T) at lower operating temperatures, but the reason for this power increase i… more
Date: June 28, 1960
Creator: Poe, J. L.
Partner: UNT Libraries Government Documents Department
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Loading and operating conditions for PT-IP-314-A, Supplement F, in KER-1

Description: Supplement F to Production Test IP-314-A authorized an upstream thermocouple train in KER-1. This document provides fuel element loadings, operating temperatures, and trip settings for two possible charges in KER-1, one using KSE-3 heater elements and the other using KSN-3 heater elements. For a charge containing KSE-3 elements, the loading and the operating conditions are given. For a charge containing KSN-3 elements, the loading and the operating conditions are given. The desired operating te… more
Date: November 28, 1960
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Contoured I&E sleeves

Description: The feasibility of contoured I&E cans for production use has been demonstrated using our present flat base I&E sleeve (HW-37187). Studies by Process Engineering and Quality Control have shown that only a material savings would result from the use of only the contoured I&E can. Consideration was then given to the use of contoured sleeves (H-3-16879) to improve the contact areas and the resulting heat transfer during fuel assembly.
Date: June 28, 1960
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
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Conversion ratio incentive for usig black mint in an E-N load

Description: This report details the proposed E-N, tritium-plutonium producing reactor loading is made up of striped columns of lithium-aluminum (mint) target slugs and enriched uranium (.947 w/o U{sup 235}) slugs. Both target and uranium slugs are of the I & E geometry. The ratio of mint (N) to uranium (E) is determined by the requirement of sufficient k-excess to sustain an operable reactor. The designer of the lattice loading has a choice between natural lithium (7-5 w/o Li{sup 6}) or lithium enriched to… more
Date: January 28, 1960
Creator: Nilson, R.
Partner: UNT Libraries Government Documents Department
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A New Liquid Explosive, NTN

Description: Abstract. The preparation and properties of a new explosive, liquid over the range -65 degrees F to +165 degrees F, are presented. This explosive, called NTN, is a 5/1/1 mole ration of nitromethane, tetranitromethane, 1 -nitropropane. The sensitivity and stability of NTN meet military requirements.
Date: January 28, 1960
Creator: Von Egidy, Albert.; Finger, Milton.; Hill, Marion.; Ornellas, Donald L.; Ellison, Edward. & Kury, John.
Partner: UNT Libraries Government Documents Department
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High Current Pulsed Electron Accelerator

Description: The most important component required for the Astron experimental facility is a high energy, high current, pulsed electron accelerator. A thin cylindrical layer of high energy electrons trapped within an axially symmetric magnetic field is the key feature of the Astron thermonuclear device. The trapping magnetic field is constant in time. Therefore, it is not possible to inject electrons and trap the electrons in this field unless during the injection phase a part of the electron energy is abso… more
Date: June 28, 1960
Creator: Christofilos, Nicholas C.
Partner: UNT Libraries Government Documents Department
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Structural Response and Permanent Displacement Measurements

Description: Measurements and visual observations made during the Hardtack II series of underground shots provide basis for conclusions regarding shock-resistant design of protection for cavities in rock and qualitative prediction of permanent displacements in rock due to nuclear detonations. Vibration measurements on blast-resistant construction in soil provided non-nuclear test results which apply to shock resistant design. With varying soil cover, the compressive mode predominated in arch structures and … more
Date: October 28, 1960
Creator: Sievers, R. H., Jr. & Stacy, A. R.
Partner: UNT Libraries Government Documents Department
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The Statistical Geometry Of Bubble Tracks

Description: An exact treatment of the structure of tracks in nuclear research emulsion recently was attempted with some success. Many of the proofs also appear to be generally valid for bubble tracks in Wilson chambers. This is a summary of the results that are applicable to tracks of charged particles in bubble chambers.
Date: September 28, 1960
Creator: Barkas, Walter H. (Walter Henry), 1912-1969
Partner: UNT Libraries Government Documents Department
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Applications for Lanthanon Oxides and Other Compounds in the Ceramic Industry

Description: Separation processes for production of pure rare earth oxides in useful quantities are discussed. A review of applications of these oxides in the ceramic industry in production of glasses, glazes, porcelain enamels, refractories, abrasives, electronic ceramics, and nuclear ceramics is also presented. 46 references.
Date: January 28, 1960
Creator: Ploetz, G. L.
Partner: UNT Libraries Government Documents Department
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9-ANGIE : a Two-Dimensional, Multigroup, Neutron-Diffusion-Theory Reactor Code for the IBM 709 or 7090

Description: The 9-ANGIE, one of a series of reactor neutronic programs for an IBM 709 or 7090 data processing system, solves the time-dependent, multi-group, neutron diffusion equation for one to eighteen energy groups applied to a rectangular mesh superimposed on either an x-y or an r-z plane. It is characterized by its generalities in region description, boundary conditions, etc., without sacrificing simplicity of input preparation and ease of machine operation. The notation, the style, and the format ha… more
Date: October 28, 1960
Creator: Stone, Stuart P.
Partner: UNT Libraries Government Documents Department
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The Nuclide Hf182

Description: The nuclide Hf182 has been made by thermal-neutron irradiation of hafnium oxide and has been found to have a half-life of 8.5 x 10(6) years. A preliminary study ha been made of possible radiations associated with the nuclide.
Date: September 28, 1960
Creator: Hutchin, W.
Partner: UNT Libraries Government Documents Department
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Tory II-A Aerothermodynamics. Part II

Description: This technical report describes the digital computer codes used for the aerothermodynamic calculations that were involved in evaluating the Tory II-A reactor.
Date: December 28, 1960
Creator: Uthe, P. M.
Partner: UNT Libraries Government Documents Department
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Hydrides of Titanium, Yttrium, and Zirconium: a Bibliography

Description: This bibliography contains 94 references on metal hydrides, with particular emphasis placed on the hydrides of titanium, yttrium, and zirconium. The bibliography covers the period 1955 through 1959. The references are arranged alphabetically by title. Sources used in compiling this bibliography are: Applied Science and Technology Index, Abstracts of Classified Reports, ASM Review of Metal Literature, Bibliographies of Interest to the Atomic Energy Program, Classified and Unclassified Parts, Ind… more
Date: April 28, 1960
Creator: Cernak, Elizabeth A.
Partner: UNT Libraries Government Documents Department
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Optimization Studies on Paste-Fueled Fast Reactors

Description: The reference design is an unmoderated, sodium-cooled reactor using a paste fuel of uranium monocarbide in sodium. The core is a cylinder 5 ft in diameter and 5 ft in height. An 18-in. thick breeding blanket surrounds the core, and an 18-in. thick graphite reflector surrounds the blanket. Various changes were made in the reference core to uncover any possible modifications for cost reductions and to evaluate the consequences of certain design modifications which might occur. Cases were studied … more
Date: December 28, 1960
Creator: Zetterbaum, J. M. & Kerlin, T. W.
Partner: UNT Libraries Government Documents Department
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HIGH-TEMPERATURE COMPATIBILITY OF Al$sub 2$O$sub 3$-, BeO-, AND METAL- COATED UO$sub 2$ PARTICLES WITH GRAPHITE AND COKE

Description: The compatibility of carbon and graphite matrices with UO/sub 2/ particles coated with Al/sub 2/O/sub 3/, BeO, nickel, niobium, and nickel- chromium alloy was investigated at several temperatures up to 3OOO deg F in flowing helium. Two different carbonaceous fillers and binders were used. As expected, the 2 to 8- mu metal coatings were badly damaged by reaction with carbon at temperatures as low as 17OO deg F. Both oxide coatings were completely destroyed after 6 hr at 3000 deg F. Considerable … more
Date: November 28, 1960
Creator: Gerds, A.F. & Smalley, A.K.
Partner: UNT Libraries Government Documents Department
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