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Zircaloy-2 process tube activity, C Reactor

Description: This report presents the dose rates which were observed during the removal of a Zircaloy-2 process tube from C Reactor. The corresponding calculated activity is also presented for the purpose of correlation with the observed dose rate. The tube was removed on July 22, 1964, after having been irradiated by a neutron flux for 560 days (based on time operated efficiency). The tube activity was monitored with a super high range TP (0-5000 R/hr) by suspending a probe through an access port in the fl… more
Date: August 26, 1964
Creator: Essig, T. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories monthly activities report, July 1964

Description: This is the monthly report for the Hanford Laboratories Operation, July 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.
Date: August 14, 1964
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel element development committee: Annual report from the General Electric Company, Hanford

Description: A summary of HAPO activities is given to include separate sections on the N-Reactor and other current production reactors. Specific programs and fuel performance for current production reactor fuels is discussed. Also, the production status, fuel performance, development program and process technology for N-Reactor fuels is presented.
Date: August 14, 1964
Creator: Lewis, M.; Minor, J. E. & Stringer, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Modified tubular support patterns: Ribbed and ribless process tubes

Description: Reactor support charge designs and patterns have been numerous and varied over the past few years, the basis for acceptance of a particular support loading being determined from a consideration of fabrication costs and the hydraulic characteristics of the proposed dummy load as it applies to a particular reactor. Since the first three or four dummy pieces downstream of the fuel column (and upstream of the column in a spline tube) are discarded after the irradiation process, it is desirable to u… more
Date: August 25, 1964
Creator: Angle, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiated Fuel Age Determination Study

Description: The release of uncontrollable quantities of harmful fission products such as I{sub 131} upon processing areas. At present this is done by procedural techniques using cards, filing techniques, and cross checks. These methods are entirely independent of the characteristics of the fuel itself and are subject to failure from human error. It is therefore advantageous to find a method of determining the age of irradiated fuel after discharge from the properties of the fuel. Such a method, with its re… more
Date: August 31, 1964
Creator: Cooley, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: July 1964

Description: This report, for July 1964 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.
Date: August 21, 1964
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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K reactor mixer study aluminum spline tubes

Description: Reference 1 gave mixer recommendations for aluminum spline tubes at the K reactors. On completion of the study, R. F. Corlett requested a more detailed economic study of mixer useage at KW reactor. R. G. Clough also requested additional information on use of mixer elements in fringe tubes. In order to answer these requests, additional information was needed and requested. A. W. Medcalf replied giving enriched metal requirements in support of mixers. No other information vas received so it was n… more
Date: August 18, 1964
Creator: Hough, C. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation analysis, PT-IP-714: Irradiation of solid aluminum in KER-1, KER-2, KER-3, and KER-4 with process water cooling

Description: This production test authorizes the irradiation of full length charges of solid aluminum in the KER loops while on single-pass operation with process water cooling. Calculations show that the irradiations will not result in any foreseen reactor or personnel hazards and can be safely performed in the KER facilities.
Date: August 27, 1964
Creator: Gerdes, K. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Through-reactor flow calculated from high tank-high velocity flush data

Description: To satisfy reactor coolant supply criteria requires a knowledge of available emergency flow rates from secondary and last-ditch systems. This document presents a method for calculating high-tank flow contribution to the last-ditch coolant system from routine high tank-high velocity flush data. The measured flush flow is converted to equivalent through-reactor flow at 20 C and at the critical time of high-tank takeover from flywheel decay.
Date: August 20, 1964
Creator: Morrissey, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

KER-2 operating report: Test K-2-22

Description: The purpose of this test was to evaluate the behavior of natural lithium-bearing materials and to provide samples for production and extraction information. Testing of the target elements was done in conjunction with a test evaluating the behavior of NIEl fuel elements. Conditions for operation during the test were similar to, or more severe, than conditions expected in N Reactor.
Date: August 3, 1964
Creator: Christensen, G. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test IP-694-A: Depleted uranium irradiation, K reactors

Description: The AEC has indicated a need for plutonium with a high concentration of the Pu-240 isotope. Concentrations up to 25 W/o Pu-240 have been requested with a firm commitment given for 25 kilograms of plutonium with at least 18 W/o Pu-240. To meet this production demand, irradiation of depleted uranium, 0.22 W/o U-235, will be undertaken. This test authorizes half of the irradiation in a Hanford K reactor, outlines the general plans, and presents the details of the irradiation. The objective of this… more
Date: August 17, 1964
Creator: Gross, P. D. & Hladek, K. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

IPD production projections. Revision

Description: The attached tables are an extension of the data that will be used in the forthcoming Production Studies. It considers thorium load substitution for the natural uranium cases previously reported. The power level, operating efficiency, exposure, conversion ratios, tonnage, and production are given for the natural U loading, blanket loading, and full conversion. The small reactors, the C reactor, and the K reactor are considered.
Date: August 3, 1964
Creator: Lang, L. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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