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High-Pressure Gamma Loop for Brookhaven National Laboratory

Description: Report issued by the Brookhaven National Laboratory discussing high-pressured gamma loops. As stated in the introduction, "this latest endeavor involved three test cells, a gamma irradiation pool and supporting equipment, as well as an enlarged high-pressure gamma loop facility" (p. 1). This report includes tables, and illustrations.
Date: June 1963
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department
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Shipboard Cobalt-60 Radiopasteurizer for Marine Products

Description: Report issued by the Brookhaven National Laboratory discussing the shipboard cobalt-60 irradiator. As stated in the introduction, "this report discusses the conceptual design of a cobalt-60 shipboard irradiator for use to improve the keeping quality of fish landed aboard commercial fishing trawlers operating out of ports along the eastern seaboard of the commercial United States" (p. 1). This report includes tables, and illustrations.
Date: June 30, 1963
Creator: Manowitz, B.; Kuhl, A. O.; Galanter, L.; Armel, J.; Black, K. M.; Klaassen, W. J. et al.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: May 1963

Description: This report, from the Chemical Processing Department at HAPO for May 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; weapons manufacturing operation; and power and crafts operation.
Date: June 21, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, May 1963

Description: This document details activities of the Irradiation Processing Department during the month of August, 1958. 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: June 14, 1963
Partner: UNT Libraries Government Documents Department
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Study of Hanford production capability through fiscal year 1973

Description: A letter dated June 3, 1963 to W, E. Johnson, General Manager, Hanford Atomic Products Operation, from J. E. Travis, Manager, Richland Operations Office requested an updated study on the expected life of existing production reactors similar to Sections II, III and IV of document HW-59000. This study covers the ten year period to FY 1973 as the previous study document covered the ten year period FY 1958 to Fy 1968. In Section II, production has been forecast for the existing plant with no improv… more
Date: June 19, 1963
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department
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Uranium burnout values

Description: Attached is the interpolated uranium burnout values Financial Consolidations will apply to the current AEC ten year cost study. We have made additional copies which may be of use to you in future studies since the source data was based on the most recent burnout schedule obtained from Washington AEC. We currently have a program to interpolate future burnout schedules. If you have a need for such a program, please contact the author.
Date: June 17, 1963
Creator: Smith, W. G.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories monthly activities report, May 1963

Description: The monthly report for the Hanford Laboratories Operation, May 1963. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics, and programming operation are discussed.
Date: June 14, 1963
Partner: UNT Libraries Government Documents Department
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Forecast reactor water leaks

Description: Reactor water leaks cause outage time for locating and eliminating the leaks and for repairing damage paused by the vater that enters the reactor. The justification for equipment and process changes necessary for reducing the number of leaks and the resultant outage time is dependent on the number of leaks expected. This document presents an estimate of the future reactor water leak frequency and the average outage time charged to each leak. A water leak is defined as any entry of vater into th… more
Date: June 3, 1963
Creator: Young, J. R.
Partner: UNT Libraries Government Documents Department
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Property evaluation of plutonium sheet used in capacitor discharge studies

Description: At the request of Lawrence Radiation Laboratory, four plutonium strips 0.050 inches thick, 0-50 inches in width and 6 inches in length have been examined by metallographic, chemical, X-ray, density and dilatometric methods. The data obtained will help calibrate high energy electrical discharge equipment used to rapidly heat plutonium.
Date: June 25, 1963
Creator: Taylor, J. M. & Gardner, H. R.
Partner: UNT Libraries Government Documents Department
open access

Comment issue N-Reactor startup physics test program test procedures -- approach to critical and minimum critical size

Description: This document describes the detailed test procedures to be used during the initial phases of the physics test program--the approach to critical and minimum critical size tests. During these initial phases, several physics characteristics of the reactor will be evaluated in addition to determination of the critical loading. Overall flux distributions will be determined in the critical pile and used to evaluate the lattice buckling characteristics. Theoretical calculations normalized to experimen… more
Date: June 24, 1963
Creator: Hagan, J. W.
Partner: UNT Libraries Government Documents Department
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Reactor physics monthly technical report, May, 1963

Description: The research and development activities reported on are: enriched fuel (1.25% U{sup 235}), flex 2 code development, Pu burning and recycle, single tube fuel element, heavy isotope production, U{sup 233} -- Th{sup 232} fuel cycle, physics input for economic studies, Pu{sup 240} effective resonance integral, N-Reactor operator certification lectures, bases for control and nuclear instrumentation, and shield evaluation. (GHH)
Date: June 3, 1963
Creator: Nichols, P. F.
Partner: UNT Libraries Government Documents Department
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Interim report III, production test IP-549-A half-plant low alum feed water treatment at F Reactor

Description: A half-plant low alum treatment test began at F Reactor on January 16, 1963. The test, which had been prompted by results obtained from a statistical analysis of fuel element ledge corrosion attack, will demonstrate whether or not high alum feed is responsible for increasing the frequency of ledge and groove corrosion attack on fuel element surfaces. The effect will be evaluated by comparing visual examination results obtained from normal production fuel irradiated in process water treated with… more
Date: June 11, 1963
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
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Results of production test IP-528-I, Supplement A: B and D Reactors` high tank drawdown test

Description: Recent high tank drawdown data obtained at F reactor during periodic high velocity flushes indicated a reduction in flow to the reactor due to building of corrosion products in the high tank discharge lines. The apparent flow reduction at F reactor was verified by conducting a high tank drawdown test. Visual inspection of B, D, and F high tank discharge lines revealed comparable densities of corrosion product buildup, and high tank drawdown data during high velocity flushes at B and D also indi… more
Date: June 5, 1963
Creator: Hollifield, P. J. & Zimmerman, P. J.
Partner: UNT Libraries Government Documents Department
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Design bases, Bauxite-sulfuric acid feed facilities 100-K area

Description: Criteria provided in this report delineate the objective, bases, and functional requirements that shall govern the preparation of detail design of the bauxite-sulfuric acid feed facilities to be installed in the 183-KE and KW Buildings. These facilities will produce the chemical coagulant used in the treatment of Columbia River water in the water plants and thus replace the existing liquid alum feed systems used for this purpose. The objective of this document is to define the operational and t… more
Date: June 10, 1963
Creator: Etheridge, E. L.
Partner: UNT Libraries Government Documents Department
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Recommended MWD factors for tritium yield predictions

Description: This document is a recommendation to change the MWD factors used by Production Computing Operation, IPD, to calculate Tritium yields from target fuel irradiated in the Hanford Production Reactors. The linear Tritium yield equations in the Nuclear Materials computer programs will not be affected by this change.
Date: June 18, 1963
Creator: Handshuh, J. W. & Vaughn, A. D.
Partner: UNT Libraries Government Documents Department
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Pressure measurements on 19-1/2 crossheader: DR Reactor

Description: Equipment Laboratory and Testing Operation was requested to measure the pressure gradient developed across a nozzle and crossheader assembly used on the rear face during reactor operation. A nozzle and pigtail assembly with pressure taps was installed on process tube 2058, and pressure taps were located at the center, at tube 2058, and at the end of crossheader No. 19-1/2. copper sensing lines were installed between the pressure tape and a tool storage area on zero level, near side of the react… more
Date: June 12, 1963
Creator: Rand, J. L.
Partner: UNT Libraries Government Documents Department
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Proposed graphite coring patterns for B, D, F, DR, and H Reactors

Description: Heat transfer calculations were performed with the aid of the IBM 7090 to determine whether or not feasible graphite channel coring patterns could be adopted at the five older Hanford Reactors. The purpose of front and rear process channel coring is to significantly reduce or eliminate net expansion of the fringe graphite by raising the operating temperature above the annealing temperature of 300{degree}C. The results of the study show that such coring patterns are possible. Also, it was found … more
Date: June 20, 1963
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
open access

Chemical decontamination of Hanford production reactors

Description: The conduct of outage work in the discharge areas of the Hanford production reactors has always been complicated by personnel exposure to radiation from the contaminants which accumulate in the effluent water piping in the course of normal operations. These containments represent trace impurities in the cooling water, together with corrosion products, which are irradiated in passing through the reactor and then deposit in the unshielded rear face piping. Radioactive residues also accumulate on … more
Date: June 27, 1963
Creator: Hauff, T. W.; Jensen, H. F. & Smith, R. H.
Partner: UNT Libraries Government Documents Department
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