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Improved Zirconium Alloys : Ninth Monthly Report Covering the Period December 1 to December 31, 1960

Description: The following report is the ninth in a series of monthly reports covering the program with the objective of developing alloys having superior 680 F water and/or 750 to 900 F steam corrosion resistance, as well as developing higher strength alloys for current temperature ranges while still maintaining corrosion resistance comparable to that of Zircaloy-2. This report was made covering the period December 1 to December 31, 1960.
Date: January 5, 1961
Creator: Weinstein, Daniel & Van Thyne, R. J.
Partner: UNT Libraries Government Documents Department
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The Preparation and Irradiation Behavior of Chemically-Nickel Plated Aluminum-Jacketed Fuel Elements

Description: Nickel plated aluminum was considered as a jacketing material for nuclear fuel elements as early as 1954, and both static and dynamic corrosion tests were carried out by Argonne National Laboratories and by Atomic Energy of Canada Ltd., employing demineralized water at temperatures of from 260 to 316{degree}C. Results generally indicated that the nickel had excellent corrosion resistance; however, difficulties were experienced in achieving satisfactory continuity and adhesion of the plate; subs… more
Date: September 5, 1961
Creator: Jacky, G. F.
Partner: UNT Libraries Government Documents Department
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Loading and operating conditions for PT-IP-401-A and PT-IP-363-A in KER-1

Description: IP-401-A authorized the irradiation of 18-inch UO{sub 2} elements and IP-363-A authorized 18-inch KSE-3 elements. This document provides specific loading and operating conditions for a charge of one UO{sub 2} element and two KSE-3 elements in KER-1.
Date: April 5, 1961
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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C-Reactor graphite burnout interim report, 1P-25A(PT-105-532-E)

Description: The oxidation of graphite in the Hanford reactors is of consequence since graphite burnout affects the strength of the moderator. As a means for indication of any highly oxidizing condition within the stack, containers or boats of small weighed samples of reactor-grade graphite are positioned along the length of an empty process channel in each reactor. The rate of oxidation of the monitoring samples, referred to as the burnout rate, is reported as percent weight lose per 1000 operating days (%… more
Date: April 5, 1961
Creator: Ryan, B. A.
Partner: UNT Libraries Government Documents Department
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Radiochemistry for the rupture of a Zircaloy-2 clad, natural uranium thermocouple fuel element in KER-1

Description: During the 0000--0800 shift on August 21, 1960, the delayed neutron monitor on KER Loop 1 indicated a high coolant activity level. Sympathetic responses were also recorded on the Loop 2, 3 and 4 monitors indicating a possible fuel element failure in Loop 1. The KER Reactor began shutdown operations immediately thereafter. The purpose of this report is to summarize the events pertinent to this reactor outage and to discuss the results obtained from coolant and coupon samples taken from Loop 1.
Date: June 5, 1961
Creator: Demmitt, T. F.
Partner: UNT Libraries Government Documents Department
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Post irradiation examination of low exposure overbore elements

Description: The uranium OD increased about 20 mils in 97W-17 and 12 mils in 96W-18. The ID did not change. Remaining cladding thicknesses of 97W-17 were 37 mils minimum and 41 mils maximum external, and 42 mils minimum and 44 mils maximum internal, excluding the A{sub l}-S{sub i}. Remaining cladding thicknesses of 96W-18 were 35 mils minimum and 45 mils maximum external, and 36 mils minimum and 45 mils maximum internal, exclusive of A{sub l}-S{sub i}. Metallographic examination disclosed small grains to a … more
Date: September 5, 1961
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
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Interim flow increases at B, D, DR, F and H reactors related to the short-range water plant modification program

Description: To provide flow increases in excess of the current water plant capacities at the old reactors, a short-range water modification program has been proposed by Facilities Engineering Section. The proposed program outlined by Facilities Engineering Section includes increased 181 and 183 building pumping capacity at B, D, and H areas, a new filter for F area, and larger impellers for the 190 building pumps at H area. It has been estimated that beneficial use for this proposed increased water plant c… more
Date: May 5, 1961
Creator: Benson, J. L. & Graves, S. M.
Partner: UNT Libraries Government Documents Department
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Production Test IP0381-A-FP, Irradiation of oversize fuel elements in the C Reactor overbored process channel facility

Description: A significant portion of the planned production.gain expected from the FY 60 Reactor Plant Improvement Program was directly related to overboring the existing graphite channels. The overbore contemplated was a modest 200 mil enlargement (which would not require enlarging the reactor shield penetrations) at those reactors which were the last to require tube replacement. This was all that appeared feasible in view of the developmental work which had been accomplished at the time the program was p… more
Date: January 5, 1961
Creator: Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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CONCEPTUAL DESIGN OF A VAPOR VOLUME FRACTION INSTRUMENT

Description: The preliminary design is described of equipment to carry out experiments on boiling burnout in which the average coolant density as a function of coolant channel length as well as local coolant densities may be measured. It appears that by use of the equipment, average densities can be accomplished in a few seconds, while determination of a complete density map (with 5% error) across a plane of the assembly requires approximately one hour. (J.R.D.)
Date: April 5, 1961
Creator: Kalos, M. H.; Davis, S. A.; Mittelman, P. S. & Mastras, P.
Partner: UNT Libraries Government Documents Department
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Electrical Limitations To Energy Resolution In Semiconductor Particle Detectors

Description: Based on the assumption that the noise contribution of a semiconductor detector is due solely to the bulk properties of the semiconductor, equations are presented which indicate the theoretical limits of noise in detector-amplifier combinations. These equations show that an optimum amplifier time constant and detector bias voltage exist for which condition the minimum noise is independent of the semiconductor resistivity. The optimum performance of a detector-amplifier system is shown to depend… more
Date: April 5, 1961
Creator: Hansen, William L. & Goulding, Frederick S.
Partner: UNT Libraries Government Documents Department
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Preparation of Thin, Self-supporting Copper Films

Description: A repeatable technique for preparation of thin, self-supporting copper films has been developed at the Lawrence Radiation Laboratory in Livermore, California. The process, done in a vacuum chamber, involves evaporation of copper by electron bombardment, and deposition of the copper on a detergent-coast glass substrate. The copper film is later removed from the substrate by immersion in water.
Date: January 5, 1961
Creator: Brunner, W. & Patton, H.
Partner: UNT Libraries Government Documents Department
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