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Unit Operations Section Monthly Progress Report - April 1960, Chemical Technology Division

Description: Progress is reported on chemical engineering research, solvent extraction, fuel cycle development, thorium studies, ion exchange, reactor fuel processing, solvent extraction, and waste processing.
Date: July 28, 1960
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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Processing Methods, Fission Product Poisoning And Fuel Cycle Costs For Fluid Fuel Reactors

Description: The fuel cycles and fuel cycle costs have been investigated for three fluid fuel breeder reactors, the aqueous homogeneous reactor, molten salt, and liquid bismuth. Estimates have been made of the fission product and proactinium poisoning, which determines the breeding ratio and doubling time or fuel yield.
Date: July 12, 1960
Creator: Burch, W. D.; Campbell, D. O. & Weeren, H. O.
Partner: UNT Libraries Government Documents Department
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Volatility Pilot Plant - Hazards Review Report

Description: The ORNL Fluoride Volatility process for the dissolution of Zr-U fuel elements in Building 3019 is described, and possible hazards and their control are discussed.
Date: July 26, 1960
Creator: Milford, R. P.; Carr, W. H.; Cathers, G. I.; Horton, R. W.; Mann, S.; Miles, F. W. et al.
Partner: UNT Libraries Government Documents Department
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Xenon Control in Fluid Fueled Reactors

Description: A comparison of methods proposed for xenon control in the three major fluid reactor types: Aqueous homogeneous, molten salt, and Liquid metal fuel reactors, indicates no significant differences in the minimum practical poison level, or the cost to achieve the level.
Date: July 6, 1960
Creator: Burch, W. D.; Watson, G. M. & Weeren, H. O.
Partner: UNT Libraries Government Documents Department
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Cesium-137 In Milk

Description: Samples of liquid milk from Bombay and 27 other stations in India, and imported powder milk from Australia, Denmark, Holland, U.K. and United States have been measured for their cesium-137 and potassium-40 contents.
Date: July 1960
Creator: Vohra, K. G.; Bhatnagar, V. S.; Mishna, U. C. & Ragupathy, S.
Partner: UNT Libraries Government Documents Department
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Solid State Division Semiannual Progress Report For Period Ending February 28, 1955

Description: This semiannual progress report and future reports will be published as two documents to permit a wider distribution of the unclassified material. The report numbers are assigned in sequence so that the two reports will fall together when filed by report number.
Date: July 12, 1960
Creator: Billington, D. S. & Crawford, J. H., Jr.
Partner: UNT Libraries Government Documents Department
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Invention Report: Hermetically Sealed Closure on a Sheathed Thermocouple

Description: Applications of sheathed (metal) thermocouples may require in many instances, the insertion of the thermocouple thermal junction into an area that must be hermetically sealed to the outside. This same area usually contains highly reactive heat transfer medium such as an eutectic alloy of sodium and potassium of sodium alone. When fissionable materials are being irradiated, fission products that are driven off would also be present and must be contained under varying temperatures and pressures.
Date: July 12, 1960
Creator: Kosut, Bert S.
Partner: UNT Libraries Government Documents Department
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A Study of the Wear and Galling of Autoclaved Zircaloy-2 By Various Materials

Description: This is the third of a series of reports describing the phases of a study of the wear and galling of autoclavedZircaloy-2 by various bearing surface materials. The first report (1) showed that increasing contact area between the autoclaved Zircaloy-2 surfaces will not prevent scratching. It also showed that metals softer than Zircaloy-2 in general do not scratch it. The second report (2) described how eight metals and alloys were wear-tested on autoclaved Zircaloy-2 as prospects for fuel elemen… more
Date: July 5, 1960
Creator: Weber, J. W.
Partner: UNT Libraries Government Documents Department
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A Model of the PRTR Mark I Fuel Element for Heat Transfer Experiments

Description: The purpose of this document is to describe the design and construction of a full-scale, electrically-heated model of a 19-rod PRTR fuel element for use in heat transfer experiments.
Date: July 6, 1960
Creator: Hammond, J. E.
Partner: UNT Libraries Government Documents Department
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Project CGC-830 Plant Modifications for Reprocessing Non-Production Reactor Fuels

Description: Facilities are to be designed for installation at Hanford for the reprocessing of irradiated, low enrichment fuels from non-production reactors, see Reference 1 and 2. The initial design of the processing facilities is to be based on processing the fuels discharged from the Dresden, Yankee, Piqua, Pathfinder and Shippingport (blanket elements only) reactors. Properties of the fuels and cladding make it impossible to completely process them in existing equipment, although the separation and deco… more
Date: July 29, 1960
Creator: Bierman, S. R.; Graf, W. A.; Kass, M.; Kligfield, G.; McKee, R.W.; Patridge, L. F. et al.
Partner: UNT Libraries Government Documents Department
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Integrated Radiological Instrumentation System Planning

Description: In recognition of the need for an integrated system plan for future development requirements for radiological instrumentation, this information report was written to provide the initial step concerning such a planning. The report is to be considered a basic information analysis of the present in-use plant radiological instrumentation, of the instrumentation now undergoing active development, and of the future development work contemplated.
Date: July 14, 1960
Creator: Spear, W. G.
Partner: UNT Libraries Government Documents Department
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Coagulant Aids as Filter Aids

Description: The Hanford water treatment plants were operated for a number of years with alum as a coagulant and activated silica as a coagulant and a polyacrylamide as a filter conditioning agent. (other polyelectrolytes may be used.) Sufficient time has elapsed to make a comparison of the two methods of operation valid and useful. Such a comparison is the purpose of this paper.
Date: July 21, 1960
Creator: Conley, W. R.
Partner: UNT Libraries Government Documents Department
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PRTR Calandria Fabrication Report

Description: The Plutonium Recycle Test Reactor is heavy water moderated with a heavy or light water reflector contained by a complex aluminum vessel called a Calandria. ( See Figure 1). Construction of this vessel started in August, 1958, at a large West Coast vendor's plant and was completed at Hanford in December, 1959. The fabrication problems associated with a high integrity welded aluminum vessel were generally unrealized prior to this period. This report covers the fabrication of the Calandria and li… more
Date: July 12, 1960
Creator: Pedersen, L. T. & Kreiter, M. R.
Partner: UNT Libraries Government Documents Department
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PCTR Measurement of EGCR Control Rod Worth

Description: This paper describes the measurement of control rod strength in the PCTR. The first section outlines the theory and method of such a measurement, and the second section presents the results of the measurement of the Experimental Gas Cooled Reactor (EGCR) control rod strength. The reactor parameter actually inferred is the difference in the infinitive multiplication factor for a control rod supercell with and without the control rod in place in the supercell. These measurements are, therefore, v… more
Date: July 20, 1960
Creator: Nichols, P. F.; Engesser, F. C. & Oakes, T. J.
Partner: UNT Libraries Government Documents Department
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Critical Tests for PRT Reactor

Description: This document authorizes the performance in accordance with the specifications noted, the PRTR Critical Tests described herein. The experiments described have the following objectives:
Date: July 1, 1960
Creator: Triplett, J. R.; Anderson, J. K.; Peterson, R. E.; Regimball, J. J.; Russell, J. T.; Schmid, L. C. et al.
Partner: UNT Libraries Government Documents Department
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Portable Radiation Instrumentation Standardization

Description: This development work was undertaken to investigate and standardize scintillation detector and transistorized circuitry techniques in instruments used for detecting and measuring alpha and beta particles, gamma photons, and both slow and fast neutrons. At the present time, the standard radiation detection instrumentation used at Hanford employ vacuum-tube circuitry with typical detectors being ion chambers, G-M tubes, HF3 tubes, etc. The vacuum tubes require excessive battery power, and some of… more
Date: July 1, 1960
Creator: Spear, W. G.
Partner: UNT Libraries Government Documents Department
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Use Of Pyroelectric Devices For Measuring Small Temperature Changes

Description: A technique for measuring extremely small temperature changes by means of a pyroelectric device is described. The sensing element is a short thin rod of polarized barium titanate ceramic with electrodes on the ends. The electric charges produced by changes in temperature are measured by a vibrating-reed electrometer. A number of calorimetric and noncalorimetric applications for the device are suggested.
Date: July 1960
Creator: Lang, Sidney B.
Partner: UNT Libraries Government Documents Department
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Strontium an Calcium Metabolism in Man, Final Report

Description: "During the first two years of this program the investigation centered around the distribution of strontium and calcium in tissues of persons who came to autopsy who had received a single tracer dose of Sr85 and Ca45. I then seemed desirable to attack some of the more dynamic aspects of strontium and calcium metabolism."
Date: July 13, 1960
Creator: Schulert, Arthur R.
Partner: UNT Libraries Government Documents Department
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Zircaloy-4 Sheet and Strip Material

Description: Scope. This specification covers Zircaloy-4 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Sheet and Strip Material

Description: Scope. This specification covers Zircalogy-2 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are quired.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-4 Tubing for Fuel Sheathing

Description: Scope. This specification covers Zircaloy-4 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Tubing for Fuel Sheathing

Description: Scope. This specification covers Zircaloy-2 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures ae required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-4 Wire Material

Description: Scope. This specification covers Zircaloy-4 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Wire Material

Description: Scope. This specification covers Zircaloy-2 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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