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Fuel element study for Reactor Overbore Program

Description: Recent studies have confirmed that large incentives exist for overboring the reactor process channels approximately 500 mils in the C and five old reactors under the proposed Plant Improvement Program. Conservative estimates of the incentives for overboring indicate a payout period of about two years for the proposed work, an increase in plutonium production of 15--18%, derived from increased conversion ratio and a reduction in plant unit cost. Since sufficient progress has been made in the are… more
Date: December 15, 1960
Creator: Stringer, J. T. & Blanton, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recommended E-N charge modification (Second cycle PT-IP-350-C E-N demonstration load)

Description: The original charge for the E-N core load at H reactor, consisting of five different types of charges, each group of five containing 199 .947 per cent enriched uranium E-pieces of six inch nominal length and 16 Li-Al I&E (N) pieces of four inch nominal length plus mixers, was intended to provide enough excess reactivity to operate the reactor at all times with reasonable but not excessive flexibility. During actual operation the excess reactivity observed has been somewhat greater than conserva… more
Date: August 15, 1961
Creator: Carter, R. D.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test IP-314-A measurement of fuel element temperature change as the result of film deposition

Description: The objective of this production test is to measure deposition on fuel element temperatures during irradiation in high pH water. A Zircaloy-2 jacketed natural uranium solid cylindrical fuel element with thermocouples located at various positions in the element and adjacent coolant channel will be irradiated in the KER Loops to measure the effect of crud film buildup on fuel temperature. Two 1.82 by 1.45 inch enriched 36 inch long tubular elements will be used to provide enough heat to permit op… more
Date: April 15, 1960
Creator: Kratzer, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation monthly activities report, March 1960

Description: This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for March 1960.
Date: April 15, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Composition of ending inventory, June 1966

Description: Submitted herewith are source and special nuclear material composition for the month of June, 1966. Normal uranium, depleted uranium, enriched uranium, plutonium, thorium, uranium-233, deuterium, enriched lithium, neptunium-237, plutonium-238, and tritium are accounted.
Date: July 15, 1966
Creator: Budd, R. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electronic Computing Gage System for Monitoring Assembly Operations

Description: An electronic computing gage with IBM card punch was found to be a practical system for monitoring the critical steps in the crimping process of the assembly of some parts. In the crimping process a plastic part is compressed into a metal cup to obtain an assembled component without gaps. Dimensional data of the plastic part and metal cup are recorded on a printed tape and on IBM cards, which are used to program a computer to calculate the standard deviation of the lot. Lot acceptance is statis… more
Date: November 15, 1969
Creator: Wendeln, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tungsten Cladding of Tungsten-Uranium Dioxide (W-UO2) Composites by Deposition from Tungsten Hexafluoride (WF6)

Description: A program is being conducted to develop a process for cladding tungsten and tungsten cermet fuels with tungsten deposited from the vapor state by the hydrogen reduction of tungsten hexafluoride. Early work was performed using recrystallized, high purity, commercial tungsten as the substrate material. Temperatures in the range 660 to 12950F (350 to 1700°C) and pressures from 10 to 350 mm Hg were investigated. Hydrogen to WF 6 ratios of 10: 1 to 150: 1 were utilized. Efforts were directed toward… more
Date: February 15, 1965
Creator: Lamartine, J.T. & Hoppe, A.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NUMBER AND TYPE OF OPERATING CYCLES FOR THE FFTF

Description: The choice of materials and other vessel design decisions necessary to provide the desired life expectancy for the FTR vessel are partially dependent upon estimates of the number and type of reactor shutdowns and startups which may be anticipated. Current estimates of these so-called "cycles" are given, including scram frequency, experimental outage frequency, standard shutdowns and startups, and rapid controlled shutdowns. Also discussed are abnormal heatup or cooldown, and tentative… more
Date: May 15, 1969
Creator: Boyd, D. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Viewing Equipment for Use in the HRT Core and Blanket Vessels

Description: S>Several viewing devices were built or purchased and various viewing aids were developed to permit examination of the core vessel of the Homogeneous Reactor Test. The hole in the core vessel was viewed and photographed from both the inside and the outside. A number of simple periscopes were designed and fabricated. A small television camera was purchased, and manipulators were built to insent it in the core or in the blanket. A radiation-resistant 21-ft-long periscope was procured which is … more
Date: March 15, 1960
Creator: Culver, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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INCR-8-Graphite-Fused Salt Compatibility Test

Description: For the purpose of evaluating the compatibility of graphite and INOR-8 in a dynamic fluoride fuel medium, INOR-8 Forced Convection Loop No. 9354-5 was operated 8850 hr. The loop operated at maximum temperature of 1300 deg F and circulated a fluoride fuel of the system LiF--BeF/sub 2/-- UF/sub 4/. Post-test examinations of the graphite and loop components revealed no apparent corrosion or carburization problems. (auth)
Date: June 15, 1961
Creator: Schulze, R. C.; Cook, W. H.; Evans, R. B., III & Crowley, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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