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Comments on Engineering Review of PRTR by Atomic Power Equipment Department

Description: On a project of the magnitude and complexity of the Plutonium Recycle Test Reactor is was considered prudent engineering practice to obtain an independant design review by a competent off-site group that had not participated in any way in the development of the design. Accordingly, the Atomic Power Equipment Department of the General Electric Company was requested to make such an engineering review, and an Assistance to Hanford contract authorizing this work was approved by the Atomic Energy Co… more
Date: October 15, 1959
Creator: Reactor and Fuels Researcg and Development Operation Hanford Laboratories Operation
Item Type: Refine your search to only Report
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Comments on Equipment for a PRTR Water Quality Control Laboratory

Description: This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating… more
Date: December 1, 1959
Creator: Anderson, H. J. & Peray, R. E.
Item Type: Refine your search to only Report
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Comparative Study of Alternative Fibrous Glass and Sand Exhaust Ventilation Air Filter Installations for Purex

Description: Unanticipated radioactive contamination of the 200 Areas environs was discovered in the latter part of 1947, about 2.5 years after the startup of the Bismuth Phosphate Separation Plants. It was subsequently established that this contamination was due to radioactive particles emanating from the Separation Plants' stacks, and the need for exhaust ventilation air filtration equipment was recognized. Sand filters were installed in the fall of 1948 in the ventilation systems of the B and T Bismuth… more
Date: December 14, 1953
Creator: Zahn, Lyle L., Jr.
Item Type: Refine your search to only Report
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A Comparative Study of Hanford and Utah Range Sheep

Description: Observations on sheep representing flocks in Utah adjacent to the Nevada Proving Ground were compared with findings made on experimental sheep exposed to various amounts of radioiodine. The Utah sheep showed no evidence of the radiation damage observed in experimentally treated sheep. Estimations of amounts of radioiodine on vegetation required to cause serious thyroid damage following a contamination event are included.
Date: November 30, 1953
Creator: Bustad, Leo K.; Marks, S.; Dockum, N. L.; Kalkwarf, D. R. & Korrberg, H. A.
Item Type: Refine your search to only Report
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Completion Report An Automatic Fuel Element Stamping Machine

Description: This document will be concerned with the design, operation and maintenance of an automatic fuel element stamping machine. In order to take advantage of automatic unloading and length checking at the Acme-Gridley lathes in the 313 Building, automatic stamping of fuel elements is desirable. This, along with the need for a permanent canning line identification, resulted in a request for a machine to automatically stamp HAPO fuel elements on a production basis.
Date: January 12, 1960
Creator: Allen, C. H.
Item Type: Refine your search to only Report
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Composition of Solids from Purex LWW

Description: The solids in Purex lww were first observed during flowsheet tests for recovery of fission products from plant wastes. Since the nature of this solid was not apparent from the flowsheet composition of lww, some work was performed to characterize this material. Although this work has been conducted over a period of about one year, it has been subordinate to the main one of testing flowsheets for fission product recovery. The solids have been observed in each of about six samples of plant lww tha… more
Date: January 22, 1959
Creator: Van Tuyl, H.H.
Item Type: Refine your search to only Report
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Computational Aids for Estimating Performance of Liquid to Boiling Water Heat Exchangers

Description: The computation of liquid-boiling heat exchanger performance under a wide variety of operating conditions is a cumbersome, time-consuming procedure. Rapid evaluation of a design requires the use of some form of computational aid. Exchanger equations covering the case of liquid-boiling heat transfer have been derived and evaluated for a specific correlation of local boiling condition. Examination of various data as presented by Bonilla and McAdams indicates that the boiling coefficients are not … more
Date: September 1, 1959
Creator: Love, W. J.
Item Type: Refine your search to only Report
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Concentration and Final Purification of Neptunium by Anion Exchange

Description: It is anticipated that neptunium will be recovered in the Purex process by solvent extraction or ion exchange methods as a nitric acid solution of greater than 0.1 g. Np/1 and containing varying amounts of fission products, plutonium, uranium, and thorium, including Th234 (UX1). At the present time this solution is thermally concentrated in the Purex L-cell package to several grams of neptunium per liter. In this operation the solution is contaminated rather badly with plutonium and stainless s… more
Date: February 10, 1959
Creator: Ryan, J.L.
Item Type: Refine your search to only Report
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Confinement System Instrumentation

Description: Instrumentation shall be provided as shown on the attached drawing, SK-1-26835 for Confinement System Control. The Primary objective of the confinement system shall be to provide maximum possible confinement of contamination, consistent with building limitations, in the event of any contamination, consistent with building limitations, in the event of any credible reactor accident resulting from equipment failure or reactor mis operation.
Date: November 6, 1959
Creator: Richards, W. A.
Item Type: Refine your search to only Report
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A Continuous Gamma Activity Monitor for the Product Stream of the Uranium Recovery Plant

Description: A continuous gamma-monitoring instrument capable of measuring the activity of the product of the Uranium Recovery plant has been developed and applied under process conditions. It has a detection limit of 15% and a normal range of up 1000% of the activity of natural uranium. Activity measurements made with this instrument have shown good correlation with laboratory determinations and are contributing to improved control of the solvent extraction process.
Date: October 1, 1953
Creator: Leboeuf, M. B.; Connally, R. E. & Upson, U. L.
Item Type: Refine your search to only Report
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Continuous Ion Exchange Development - A Qualitative Review

Description: Considerable interest has developed in the use of ion-exchange in the nuclear energy field in the last decade. Aside from the obvious use of providing demineralized coolant water for reactors, the projected uses of ion-exchange include the recovery of fission products from aquaeous waste streams and the separation and purification of fissionable materials from spent reactor fuels. The latter process may be incidental to the over-all operation, as is the case with the Purex anion exchange facili… more
Date: November 10, 1959
Creator: Nicholson, G. A.
Item Type: Refine your search to only Report
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Contraction Losses and High Temperature Pressure Drop Determinations for Tube Bundles

Description: In some engineering applications it has become necessary to operate equipment containing small diameter rods or tubes oriented parallel to flow stream. In the case of several nuclear reactors such as the Plutonium Recycle Test Reactor and the S. S. Savannah Maritime Reactor, bundles of small diameter rods are used as the fuel elements. The situation also has application to heat exchangers. A method for accurately predicting the pressure drop characteristics of various bundle configurations woul… more
Date: January 25, 1960
Creator: Gartin, W. J.
Item Type: Refine your search to only Report
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Controlled Temperature Irradiation of Graphite Interim Report No. 4. PT-IP-22A

Description: Property changes to common graphites resulting from reactor irradiation depends strongly on the temperature of exposure. Radiation affects at 30 C and 400 to 500 C are quite well known; however, at intermediate temperatures, results are not well known although a large volume of graphite in most reactors operate in this range. Production test, IP-22A, was reactivated, after a dormant period of many months, to study radiation damage between 30 and 400 C. This report concerns mainly the experiment… more
Date: October 21, 1959
Creator: Koyame, K.
Item Type: Refine your search to only Report
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Correlation of Chemical Analyses on Graphite Bars and Test Pile Results

Description: From abstract: "The chemical analyses of graphite test bars obtained from National Carbon Company and the analyses performed by the Hanford Works Laboratories Division do not correlate significantly with the test pile results, nor do the chemical analyses obtained from National Carbon Company agree with those done in the Handford Works Laboratories. Chemical results obtained at Hanford on samples taken lengthwise from individual bars correlated significantly with the individual test pile result… more
Date: February 5, 1948
Creator: Lane, J. J.
Item Type: Refine your search to only Report
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Correlation of Exponential and PCTR Measurements of Cluster Fuel Elements with Theory

Description: Accurate knowledge of the lattice parameters comprised in the four factor formula k∞=η∈Pi are required for optimum designing of reactors. In the special case of cluster fuel elements conventional handbook formulas are of little use. It is the intent of this paper to report the results of some recent improvements in the calculation of these parameters. By the addition of certain refinements in the calculation of these parameters. By the addition of certain refinements to the conventional calcula… more
Date: December 31, 1958
Creator: Joanou, G. D.
Item Type: Refine your search to only Report
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