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Critical-Assembly Experiments on a Reflector Control System for a Boiling Reactor

Description: Research directed toward an evaluation of a reflector control scheme for a small boiling heterogeneous reactor is reported. The control method uses the ambient reactor steam pressure to adjust the height of a radial water reflector. Critical-assembly experiments were conducted to measure the reflector worth and the effect of nonhomogeneous voids. The critical-assembly core approximated a right circular cylinder 24 in. high and 21 in. in diameter. The core was made up of polyethylene strips to s… more
Date: December 20, 1957
Creator: Dingee, David A.; Hogan, William S.; Wilson, Robert G.; Ballowe, William C.; Jankowski, Francis J. & Chastain, Joel W.
Partner: UNT Libraries Government Documents Department
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A critical review of alternate methods of Purex solvent treatment

Description: This document is a HAPO report dated September 20, 1957. At the time of this report, there had been many different methods suggested for improving the Purex organic recovery system. Some of these suggestions been tried in the plant and others had not. Information concerning this system and, particularly, methods for improving it were wide spread. At the time of this report was no immediate source of information available on the proposed and investigated methods for improving the Purex solvent r… more
Date: September 20, 1957
Creator: Gordon, N. R.
Partner: UNT Libraries Government Documents Department
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Flowsheet No. 1: Cesium isolation and packaging

Description: An engineering flowsheet has been prepared for the conversion of an aqueous slurry of cesium-zinc-ferrocyanide into a dry cesium chloride product by the calcination process. Flowsheet No. 1 defines a six-step batch-type calcination operation for processing the slurry into a dry powder for offsite shipment in bulk containers. Some of the advantages to this process are as follows: Product losses are expected to be small, estimated to be less than 0.03 percent; the equipment required to process a … more
Date: May 20, 1957
Creator: Wirta, R. W. & Koski, O. H.
Partner: UNT Libraries Government Documents Department
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Fuels Preparation Department monthly report for November 1957

Description: This report describes the operation of the fuels preparation department for the month of November 1957. Manufacturing employee relations, process development, plant improvements and financial operations are described.
Date: December 20, 1957
Partner: UNT Libraries Government Documents Department
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Graded Plate Cartridge for Purex A-Type Extraction Column

Description: Graded nonuniform cartridges are described which have plates with larger holes, greater free area, and/or greater plate spacing. These plates were developed and specified for the Purex Plant A-type columns. Use of the cartridges eliminated cyclic local flooding and increased the complete flooding frequency by 10 and 25 cycles/min at volume velocities of 530 and 1060 gal/hr/ sq ft, respectively, and exhibited satisfactory extraction efficiency over a wide range of frequencies and throughputs. (a… more
Date: March 20, 1957
Creator: Geier, R. G. & Hesson, G. M.
Partner: UNT Libraries Government Documents Department
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Hot semiworks summary: Run PX-18

Description: Hot Semiworks Run PX-18 was made to compare HA Column decontamination using HAF prepared by either updraft, or downdraft dissolving. Also determined were the effects on IA Column performance of (1) using Versene washed solvent, and (2) of addition Versene to the IAF and IAS. The Purex plant low-acid flowsheet was used during PX-18. No change in HA Column decontamination was noted which could be directly attributed to the change from updraft to downdraft dissolved feed. However, HA Column decont… more
Date: March 20, 1957
Creator: Murray, J. L. & Sloat, R. J.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly record report, August 1957

Description: This document details activities of the Irradiation Processing Department during the month of August, 1957. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and engineering; operations; production and reactor operations; facilities engineering operation; employee relations operation; and financial operation.
Date: September 20, 1957
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly record report, July 1957

Description: This document details activities of the irradiation processing department during the month of July, 1957. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations: Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: August 20, 1957
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly record report, November 1957

Description: This document details activities of the irradiation processing department during the month of November 1957. A general summary is included at the start of the report, after which the report is divided int the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: November 20, 1957
Partner: UNT Libraries Government Documents Department
open access

Irradiation Processing Department Monthly Record Report: October 1957

Description: This document details activities of the Irradiation Processing Department during the month of November, 1957. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: November 20, 1957
Partner: UNT Libraries Government Documents Department
open access

OMR NUCLEAR PARAMETER SURVEY

Description: A parameter survey was conducted on the Organic Moderated Reactor (OMR) to determine the nuclear effect of temperature, enrichment, fuel to moderator volume ratio, fuel element size, ard fuel element container variation. Temperatures ranged from 300 to700 deg F; enrichments from 1.5 to 1.9%; and fuel to moderator volume ratios from 0.1333 to 0.545. Fuel element sizes of 3.75, 4.5, and 5.5 in. were considered. The stainless steel fuel element container thickness was varied from 20 to 80 mils, an… more
Date: August 20, 1957
Creator: Davis, W.W. & Leggett, W.D.
Partner: UNT Libraries Government Documents Department
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Semi-Annual Summary Research Report in Metallurgy for January-June 1957

Description: Study of the equilibrium phases which exist in Mg-rich alloys of the Mg-- U--Th system was continued. The precipitation of thorium as thorium dihydride from thorium-magnesium solutions was investigated over the temperature range 665 to 810 deg C. Soft, ductile niobium metal can be prepared by mixing essentially stoichiometric quantities of Nb/sub 2/O/sub 5/ and carbon, but slight deviation from stoichiometry yielded metal which was hard and non-ductile. The Zn vapor pressures over a number of Z… more
Date: December 20, 1957
Partner: UNT Libraries Government Documents Department
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Separation plant effluent gas measurements for determining plutonium production rate

Description: The use of ion chambers or proportional beta counters is recommended for the measurement of Kr{sup 85} in separations plant gaseous effluent. It will be necessary to evaluate the Xe{sup 133} present if short cooling times (less than about 90 days) since irradiation are used. This can be accomplished through calibration and decay measurements. It is concluded that the Kr{sup 85} evolution could be determined to about {plus_minus}5% with careful measurements.
Date: May 20, 1957
Creator: Schwendiman, L. C.
Partner: UNT Libraries Government Documents Department
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STUDIES RELATING TO HYDROGEN IN DINGOT URANIUM

Description: The distribution of H/sub 2/ among feed materials and products in the thermite reaction producing dingot U was studied. The H/sub 2/ content of Mg, molten U, and molten and solid MgF/sub 2/ density oxide to 98 to 99% for the high specific surface, ow bulk density oxides. The observed values for properties of the U/sub 3/O/sub 8/ samples correlated better with conversion of U/ sub 3/O/sub to UF/sub 4/ than did the observed values for properties of the corresponding UO/sub 2/ intermediates. (auth) more
Date: September 20, 1957
Creator: Trzeciak, M.J. & Mallett, M.W.
Partner: UNT Libraries Government Documents Department
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Test of HRT Recombiners

Description: Tests of the HRT fuel and blanket recombiners at several gas concentrations and steam rates disclosed satisfactory efficiency at approximately design conditions. At lower gas concentrations and steam fiow rates a small recombiner downstream from the condenser is necessary to maintain 100% recombination. It is recommended that the platinized catalyst in the fuel and blanket HRT recombiners not be replaced, and that a small recombiner be installed in the 1-in. off-gas line from each recombiner co… more
Date: September 20, 1957
Creator: Hannaford, B. A.
Partner: UNT Libraries Government Documents Department
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