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PREPARATION AND FABRICATION OF PLUTONIUM FUEL ALLOY FOR LOS ALAMOS MOLTEN PLUTONIUM REACTOR EXPERIMENT NO. 1

Description: Tantalum-sheathed plutonium fuel pins were prepared for the first core loading of the Los Alamos Molten Plutonium Reactor Experiment-I. Plutonium--10 at.% iron alloy was prepared by co-reduction and by co-melting methods. After casting the alloy into rods, each rod was machined and finished to a 0.357-in.- diameter piece weighing 175 g. The finished alloy rod was finally placed in a tantalum sheath, then sealed by fusion welding to a tantalum cap. Procedures and equipment used for alloying, cas… more
Date: April 15, 1960
Creator: Anderson, J.W.; McNeese, W.D. & Leary, J.A.
Partner: UNT Libraries Government Documents Department
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FUEL BURNUP STUDIES FOR A 225 Mwe ADVANCED SODIUM GRAPHITE REACTOR

Description: Reactivity and fuel burnup studies were performed for a 255 Mw(e) sodium- graphite reactor of the advanced calandria core type. This reactor is briefly described. Initial criticality calculations and flux distributions were obtained, using two-group theory for enrichments between 2.0 at.% U/sup 325/ and 4.0 at.% U235. A four-group burnup study was performed for enrichments between 2.5 at.% Uisup nd 3.25 at.% U/sup 235/. Core lifetime, changes in isotopic fuel composition, variations in radial p… more
Date: June 15, 1960
Creator: Aronson, A. L.
Partner: UNT Libraries Government Documents Department
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A LINEAR INDUCTION PUMP FOR LIQUID METALS

Description: A linear induction pump of a special design was used to circulate molten sodium through a mockup of an experimental "overflow" type of sodium-cooled reactor. The distinctive features of this pump are that no seals or moving parts are required: no piping is required to carry sodium to the pump or away from it because the pump is mounted directly on the reactor vessel, with the windings outside of the vessel and the magnetic flux return path inside the vessel. The pump develops 342 gpm at 6.2 psi… more
Date: January 15, 1960
Creator: Baker, R.S.
Partner: UNT Libraries Government Documents Department
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Compatibility of SNAP Fuel and Clad Materials

Description: Samples capsules containing buttons of materials of interest for SNAP fuel elements were held at temperatures up to 1600°F , in hydrogen, under a 20-tsi load for 200+ hours.
Date: October 15, 1960
Creator: Balkwill, J.K.
Partner: UNT Libraries Government Documents Department
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Progress letter No. 11 for January 1, 1960 through January 31, 1960

Description: A stainless steel autoclave for superheated water corrosion test was installed and "conditioned". Tests were begun to investigate the feasibility of densifying slip cast stainless steel by means of liquid phase sintering. Attempts to prepare tubular fuel elements by vacuum forming were resumed. Although thick-walled vacuum formed casting have been sintered on the aluminum mandrels without cracking, this has not yet been accomplished with the think sections of interest.
Date: February 15, 1960
Creator: Baron, Edeard H.
Partner: UNT Libraries Government Documents Department
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SELECTION OF THE PIQUA OMR FUEL ELEMENT

Description: Two types of aluminum-clad uranium alloy fuel elements, a square (parallel flat plate) and a circular (concentric cylindrical shell) were investigated to determine their relative suitability for use in the Piqua Reactor. Nuclear, thermal, and mechanical data are given, and considerations leading to selection of the circular element are presented. Design dimensions are listed and reactor thermal design and operating conditions are given for the proposed element. (auth)
Date: March 15, 1960
Creator: Baumeister, E.B. & Wilde, J.D.
Partner: UNT Libraries Government Documents Department
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Upper Atmosphere Monitoring Program : Progress Report No. 8 for May 1, 1959 through July 31, 1959

Description: The overall scope of the program encompasses both research into the physical parameters involved in the collection of airborne radioactive particles and the development, fabrication and calibration of balloon-borne sampling equipment to enable the precise determination of stratospheric particle concentration and particle size distribution.
Date: January 15, 1960
Creator: Baumstark, J.; Jones, S.; Stern, S.; Torgeson, L. & Zeller, W.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: July 1960

Description: This document presents a summary of work and progress at the Hanford Engineer Works for July, 1969. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project sections… more
Date: August 15, 1960
Creator: Bennett, C. A.
Partner: UNT Libraries Government Documents Department
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Sampling and Analytical Data on Al-Pu Alloy for PRTR Start-Up Tests

Description: In answer to the question, "How well do we know the composition of the fuel material for the PRTR start-up tests?", the analytical data on the PRTR fuel elements and other fuel elements which were fabricated by similar processes was gathered and analyzed. The results of this analysis are presented.
Date: June 15, 1960
Creator: Bloomster, C. H.
Partner: UNT Libraries Government Documents Department
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Thermoelectric Materials. Final Report, January 28, 1959-July 28, 1960

Description: BS> A method for the measurement of thermal conductivities of electrically conducting materials at temperatures in excess of 1000 deg C with a high accuracy was devised. The spatial boron concentration gradient in boron- doped graphite to achieve maximum p-type thermoelectric output was established. The production of an n-type silicon carbide-graphite composit was studied. Theoretical studies produced a detailed picture of the effect of doping on the electronic properties of graphite. A method … more
Date: August 15, 1960
Creator: Brechenridge, R. G.
Partner: UNT Libraries Government Documents Department
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Water plant modifications for increased production at B, C, D, DR, F, and H Reactors

Description: The purpose of this report is to define the extent of modifications necessary to increase capacities of the 100-B, C, D, DR, F, and H water plants for reactor flows of 90,000 95,000 105,000 and 115,000 GPM, and to provide supporting data for budget studies for increased production.
Date: April 15, 1960
Creator: Brinkman, L. B. & Corley, J. P.
Partner: UNT Libraries Government Documents Department
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Gamma activity of irradiated zircalloy samples

Description: Three small samples of zircalloy-2, obtained from a KER tube, were irradiated in the Quickie Facility in F Reactor for one, four, and nine months, respectively. Each sample weighed approximately two grams. One day after discharge from the reactor, the specific activity of each of the samples was essentially the same (about 150 mr/hr/gram at one foot in air). Attenuation measurements taken one day after discharge using lead plates yielded a ten-fold reduction in gamma intensity for each 0.95 inc… more
Date: June 15, 1960
Creator: Bunch, W. L.
Partner: UNT Libraries Government Documents Department
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Cap-spire pulsing

Description: The cap-spire pulsing technique of preheating the cap-spire portion of the fuel assembly does significantly improve the brazing of the cap-spire assembly. The air pocket at the spire wafer junction is fully removed. The cap side wafer is essentially 100% wetted with brazing alloy. Destructive tests show that a 4 to 1 improvement in most quality measurements is achieved over present cap preheating techniques, without using additional cleaning step of spire etching. The pulsing is accomplished by… more
Date: June 15, 1960
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
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Magnetic Recorder for Nuclear Pulse Application : Covering the Period from February 6, 1960 to April 5, 1960

Description: Abstract: "The accuracies which can be achieved in analog recording systems are for the most part tape limited. While reasonable variations in tape speed do not directly affect the accuracy, such variations result in improper tape tensioning, which in turn results in poor head-to-tape contact. The quality of the tape transport mechanism should be such that the error introduced by improper head- to tape contact is less than tape errors. Some additional equipment is necessary in setting up a tape… more
Date: April 15, 1960
Creator: Burgwald, G. M.
Partner: UNT Libraries Government Documents Department
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MAGNETIC RECORDER FOR NUCLEAR PULSE APPLICATION. Period covered: February 6 to April 5, 1960

Description: The accuracies which can be achieved in analog recording systems are for the most part tape limited. While reasonable variations in tape speed do not directly affect the accuracy, such variaticns result in improper tape tensioning, which in turn results in poor head-to-tape contact. The quality of the tape transport mechanism should be such that the error introduced by improper head- totape contact is less than tape errors. Some additional equipment is necessary in setting up a tape recorder fo… more
Date: April 15, 1960
Creator: Burgwald, G.M. & Norton, R.M.
Partner: UNT Libraries Government Documents Department
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Unique Fabrication Processes Applied to Fuel Cladding Materials

Description: The fabrication processes applied to nuclear fuels are subject to severe limitations because of the conditions imposed by the reactor environment. The combined problems of neutrons fluxes, high heat fluxes, corrosion by the coolant , and embrittlement by hydriding or similar reactions may be minimized through establishing rigorous materials and fabrication specifications for fuel and cladding.
Date: March 15, 1960
Creator: Bush, S. H.
Partner: UNT Libraries Government Documents Department
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In-reactor rupture testing of Zircaloy-2 clad seven-rod cluster fuel elements

Description: Three tests have been run in the ETR in high temperature, high pressure, recirculating water. In one test, previously unirradiated fuel elements were used and in the other two the fuel was irradiated to 2400 MWD/T at HAPO prior to insertion in the ETR. Failure was initiated by shearing off a projection on the surface of one rod of a fuel element, thus opening a 25-mil hole through the cladding. The projection was sheared off by a hydraulically operated chisel controlled from outside the reactor… more
Date: April 15, 1960
Creator: Call, R. L. & Kaulitz, D. C.
Partner: UNT Libraries Government Documents Department
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An appraisal of the Hanford high-level waste program

Description: As set forth in the CPD Waste Management Program (HW-63958), new and improved methods of waste processing are planned to be initiated at Hanford. A major part of this program is concerned with the high-level wastes from the Purex Plant, with major objectives being the control of long-term hazards, the insurance of production continuity, and the attainment of positive waste accountability at reasonable over-all costs. Specific plans for the disposal of Purex wastes are based on the use of high t… more
Date: September 15, 1960
Creator: Campbell, B. F.
Partner: UNT Libraries Government Documents Department
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