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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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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-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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Reactor-Grade Zircaloy-4 Ingot

Description: Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-4, and intended for the production of reactor components.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Reactor Grade Zircaloy-2 Ingot

Description: Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-2, and intended for the production of reactor components.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Critical Experiments with Oxide Fuel Pins

Description: This report describes the critical experiments with pin-type oxide fuel elements for the Consolidated Edison Thorium Reactor (CETR). This report also describes the measurements and gives a brief interpretation of the results in some cases
Date: July 1960
Creator: Batch, M. L. & Snidow, N. L.
Partner: UNT Libraries Government Documents Department
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Consolidated Edision Thorium Reactor Physics Design

Description: The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and power density distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor.
Date: July 1960
Creator: Barringer, H. S.; Flickinger, R. B. & Spetz, S. W.
Partner: UNT Libraries Government Documents Department
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Thermal and Hydraulic Design of the Consolidated Edison Thorium Reactor

Description: This report presents the thermal and hydraulic analyses, both steady state and transient, for the CETR. Methods of calculations are discussed and results of analyses are presented. Steady state analyses are included for: pressure drops, flow distribution, orificing, burnout, fuel central melting, local boiling, and bulk boiling. Transient analyses are performed for several loss of forced coolant flow incidents.
Date: July 1960
Creator: Ferrell, J. K. (James K.); Flora, H. E.; Hostetler, D. R.; Stanek, L. J. & Vannoy, W. M.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor: Reactor Vessel Internal Components Design

Description: The design functions and fabrication details for internal components of the CETR are presented and pertinent analytical stress studies are summarized. Functions of the internal components include proper orientation and support for the fuel elements, proper distribution of primary coolant within the reactor vessel, and the establishment of guide channels for the control rods.
Date: July 1960
Creator: Ficor, J.; Collings, D. M.; Sandrock, R. J. & Kalen, D. D.
Partner: UNT Libraries Government Documents Department
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Control Blade Worth by Partial Water Height and Soluble Boron Methods

Description: The series of experiments described in this paper was performed to determine reactivity values of various patterns of fully inserted cruciform control blades. The experiments yielded the worth of fully inserted blade patterns in terms of their holddown characteristics.
Date: July 1960
Creator: MacKinney, Arland L. & Ball, Russell M.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: June 1960

Description: This is the monthly report for the Hanford Laboratories Operation, July 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities,, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: July 15, 1960
Partner: UNT Libraries Government Documents Department
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Hanford Operations Office monthly status and progress report. Part 1

Description: This is the monthly report for the Hanford Laboratories Operation, July, 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: July 1, 1960
Creator: Travis, J. E.
Partner: UNT Libraries Government Documents Department
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Duplex bath variables experiments

Description: No Description Available.
Date: July 20, 1960
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
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Variable goal exposure plans for production type fuel elements

Description: The purpose of this memorandum is to transmit revisions to the goal exposure plans of reference (1). The plans, herein, supersede the previous recommendations. Similar to the plans of reference (1), the exposures calculated from these plans are designed to maximize plant return on the basis that the only restraint on metal usage is that imposed by the economics of the plutonium production process and associated uranium cycle, as described and defined in references (2) and (3). When metal throughput is limited by ex-reactor physical capabilities to a level lower than the unrestrained requirements, exposures higher than those recommended in this document would be indicated, as explained in reference (4). In essence then, these plans represent minimum economical exposures for current production fuel types, on the basis of attempting to maximize plant returns. The adjustments recommended herein, stem solely from revised estimates of the metal performance level indices (C{sub R} values) of the various metal types.
Date: July 6, 1960
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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Irradiation summary report - PT-IP-288-A, evaluation of seven rod cluster elements with modified end closures

Description: The objective of this report is to summarize all in-reactor operating data associated with PT-288-A. This document will serve as a ready reference to the irradiation history of the fuel elements, and will record any anomalies encountered in the performance of this test.
Date: July 13, 1960
Creator: Kratzer, W. K. & Peacock, D. W.
Partner: UNT Libraries Government Documents Department
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Design of supplement B to PT-IP-262-A-11-FP, evaluation of projection fuel elements for use in ribbed process tubes

Description: One of the three major categories of HAPO fuel element failures is the side corrosion type rupture. The majority of side-corrosion failures has been characterized by oval or tear-drop shaped flow patterns containing evidence of accelerated corrosion. Thorough examination of many of these so-called `hot spot` failures has indicated the failure was caused by poor heat transfer associated with misalignment, dimensional distortion or poor jacket-to-core bonding. It has been postulated that misalignment of the fuel element is a necessary condition for formation of hot spots under the present reactor operating conditions. Neither tru-line contours nor X-8001 alloy are successful in the prevention of misalignment and associated ruptures; therefore, it has been proposed to test the effectiveness of projections on the side of the fuel element toward preventing fuel misalignment in ribbed process tubes. A previous test of this element termed the `bumper fuel element` was encouraging; however, it failed to provide the conclusive proof required to justify a large-scale demonstration loading. Supplement A to the basic test was written to obtain necessary preliminary data. This report presents an outline of further testing required to accelerate evaluation of the bumper concept.
Date: July 18, 1960
Creator: Hodgson, W. H. & Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, June 1960

Description: This document details activities of the irradiation processing department during the month of June 1960. 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: July 15, 1960
Partner: UNT Libraries Government Documents Department
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Supplement D, Production Test IP-314-A, measurement of fuel element temperature changes as the result of film deposition

Description: The thermocouple train is modified by the substitution of one eighteen-inch enriched and four twenty-four inch natural uranium tubular elements for the two thirty-six inch enriched tubular elements used on the original thermocouple train. The operating limits for the loading have been changed because of the change in charge power. This supplement also authorizes the addition of fuel elements upstream of the thermocouple train if the thermocouple element and heater elements do not provide enough heat to operate the loop at the desired temperature.
Date: July 29, 1960
Creator: Kratzer, W. K. & Peacock, D. W.
Partner: UNT Libraries Government Documents Department
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