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Effects of the Maximum Credible Accident Relevant to the Design of the Containment Shell, Experimental Low-Temperature Process Heat Reactor Project

Description: The effects of the maximum credible accident relative to the design of the containment shell are discussed. The maximum credible accident is defined. The thermal and hydraulic effects of the maximum credible accident on the reactor system were analyzed. The extent to which fuelrod cladding will melt was estimated. The amount of energy released from the reactor system by the escaping steam and water and by a possible chemical reaction was calculated along with the corresponding pressure rise inside the containment shell. The kinds, amounts, and total radioactivity of fission products released to the atmosphere of the containment shell after the core melts were predicted. (M.C.G.)
Date: March 21, 1960
Partner: UNT Libraries Government Documents Department
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Southwest Retort, Volume 12, Number 7, March 1960

Description: This publication of the Dallas-Fort Worth Section of the American Chemical Society includes information about research, prominent scientist, organizational business, and various other stories of interest to the community. Published monthly during long academic semesters.
Date: March 1960
Creator: American Chemical Society. Dallas/Fort Worth Section.
Partner: UNT Libraries
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Proposal for an Advanced Engineering Test Reactor : ETR II

Description: Report containing "the results of a study which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR or in existing commercial test reactors" (p. 5).
Date: March 17, 1960
Creator: deBoisblanc, D. R.
Partner: UNT Libraries Government Documents Department
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Zero Power Experiments for the SM-1 Core II : Task XV

Description: Abstract: An element by element reactivity check for SM-1 Core II fuel elements and control rod absorber sections was performed and the burnable nuclear poison loading in the SM-1 Core II stationary fuel elements was established. An approach to criticality of the SM-1 Core II was performed by the inverse multiplication method and the critical rod bank position obtained as a function of fuel loading up to the full SM-1 Core II loading. Maximum and minimum core reactivity measurements were obtained by selective loading of stationary fuel elements and the total "excess K" for the core established. Power distribution measurements in the region of the core-reflector interface and the fuel-absorber interface in the control rod assemblies were performed. The effectiveness of europium flux suppressors in the top of control rod fuel elements and the power peaking in stationary elements adjacent to water gaps in control rod assemblies were measured. Survey measurements established the worth of spiking cold clean SM-1 cores with SM-2 elements, and of water holes in the SM-1 core which might be utilized as flux traps for materials irradiation.
Date: March 15, 1960
Creator: Robinson, R. A.; Weiss, S. H.; McCool, W. J. & Schrader, E. W.
Partner: UNT Libraries Government Documents Department
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Qualification Approval Tests on resistance products Co.`s type {open_quotes}H{close_quotes} Carbon Composition resistors (0.2 and 40 Megohm)

Description: Engineering Work Requests ESE-48 & 49 established a program for performance of Qualification Approval Tests on RPC`s 0.2 and 40 meghom Carbon Composition Resistors. This report is an accounting of these tests wherein (50) samples of each component were subjected to QA tests per drawings 8O2C250 and 802C251. Tests are explained and results tabulated.
Date: March 25, 1960
Creator: Dixon, L.W.
Partner: UNT Libraries Government Documents Department
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Cathode brazing control for GEXF

Description: As a result of repeated epidemic losses of brazed cathodes at GEXF, the engineering work necessary to determine the best brazing cycle and the controls necessary to insure reproducibility and high yields in the future was carried out by means of EN-297. Included are the procedures used and the tests made to verify the conclusions drawn and the recommendations made.
Date: March 8, 1960
Creator: Thinnes, E.L.
Partner: UNT Libraries Government Documents Department
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LRL background measurements program for ICBM discrimination

Description: Several proposals have been made for discriminating between Intercontinental Ballistic Missiles (ICBM) and decoys. Primary fundamental particles or high energy electromagnetic radiation can be scattered from or can activate the targets. The secondary radiation is observed by directional detectors that are positioned close-by and the information is transmitted to control centers on the ground. Lawrence Livermore Laboratory proposes a program for measurements of the natural space radiations. Eventually, the space backgrounds must be measured before a satisfactory discrimination system can be perfected. Past and scheduled background measurements are described and a measurement program is proposed.
Date: March 9, 1960
Partner: UNT Libraries Government Documents Department
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Manual of Radiation Protection Standards

Description: "The following is an alphabetical listing of terms and units in common usage at Hanford Atomic Products Operation. Other terms and definitions may be added as the need becomes apparent or as revisions or additional terms are issued by the NCRP and ICRP."
Date: March 1, 1960
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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Summary of KER-1 operation, February 15, 1958--March 1, 1960

Description: Recent borescoping of the KER-1 tube revealed several scratches, pits, and gall marks on the internal wall of the tube. These deformations could limit the operating temperature and pressure of KER-1. This report is a summary of operating history and is compiles to assist in determining what contributed to the condition of the tube.
Date: March 3, 1960
Creator: Buckner, C. L.
Partner: UNT Libraries Government Documents Department
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Some considerations concerning the accuracy of power level calculations in the context of the control of SS materials

Description: This report investigates a study of the accuracy of the power level calculations. Some characteristics of this calculation can be adduced but the accuracy in the sense of freedom from bias leads to an impasse. It presumes that there is another measurement for comparison purposes for which there are engineering reasons to believe, the inherent error is smaller. For the power level values as calculated by the Foxboro Power Level Calculator no such measurement or calculation exits. However, the calculations can be studied to determine whether it is worth-while to make further refinements relative to the various functions of the power level calculation. The accuracy requirements vary according to use where the most stringent requirements are in the control of SS Materials.
Date: March 14, 1960
Creator: Stewart, K. B.
Partner: UNT Libraries Government Documents Department
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Properties of High-Temperature Ceramics and Cermets: Elasticity and Density at Room Temperature

Description: From Introduction: "The present paper contains detailed descriptions of the methods used in calculating both the elastic constants and the statistical parameters. These detailed descriptions have been included for two reasons: (1) To leave no doubt as to the exact procedure, and (2) to act as a guide to other workers who might wish to make similar determinations."
Date: March 1, 1960
Creator: Lang, S. M.
Partner: UNT Libraries Government Documents Department
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Alpha correlation

Description: This study was developed to provide a correlation for the evaluation of the pile C{sub RI}/Tube C{sub RI} ratio (alpha value) for each of the Hanford reactors.
Date: March 24, 1960
Creator: Cremer, B. R.
Partner: UNT Libraries Government Documents Department
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Hydraulic demand curves for standard BDF geometry at low tube powers

Description: Information concerning the pressure-flow relations in reactor process tubes at very low heat generation rates is of value for determining flow requirements during shutdown conditions. Since such information is quite difficult to calculate when boiling occurs, a brief laboratory investigation was conducted to obtain experimental data. The data obtained for BDF geometry are recorded in this report for distribution to those persons having an interest in the application of the results to reactor operation.
Date: March 24, 1960
Creator: Waters, E. D. & Fitzsimmons, D. E.
Partner: UNT Libraries Government Documents Department
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Status report - C Reactor process tubes

Description: Data have recently been obtained on a number of C-Reactor process tubes. These data make is possible to reassess the current conditions of the tubes in the C-Reactor and hence to re-evaluate the probable data when retubing of the reactor will have to be started. The results of this reassessment are presented below.
Date: March 21, 1960
Creator: Miller, N. R.
Partner: UNT Libraries Government Documents Department
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Conductive Flooring for Hospital Operating Rooms

Description: Report issued by the Bureau of Standards over studies on the importance of conductive flooring in hospitals. Types of conductive flooring are compared, and tested. The methods and results are presented, and discussed. This report includes tables, illustrations, and photographs.
Date: March 21, 1960
Creator: Boone, Thomas H.; Hermach, Francis L.; MacArthur, Edgar H. & McAuliff, Rita C.
Partner: UNT Libraries Government Documents Department
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An assessment of the zirconium tube program -- C Reactor pilot demonstration installation

Description: Production Test IP-272-A-FP authorizes the installation of up to 100 smooth bore Zircaloy-2 process tubes in C Reactor to demonstrate the feasibility of self-supported fuel elements for production use. An additional 200 zirconium tubes are expected to be delivered by mid-year and con be used to expand the initial demonstration facility. It is the purpose of this document to assess the status of the pilot demonstration program from the B-C Reactor Operation viewpoint.
Date: March 18, 1960
Creator: Amy, G. O.
Partner: UNT Libraries Government Documents Department
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Travel to Oak Ridge and Savannah River Plant to Study Processing Plant Containment Philosophy. Trip Report, January 26--29, 1960

Description: This report discusses travel to the Oak Ridge National Laboratory on January 26 and 27 and the Savannah River Laboratory and Plant on January 28 and 29, 1960. The primary objectives of the trip were to obtain information on the containment philosophy for processing plants recently adopted by Oak Ridge National Laboratory and on the Palm Program at Savannah River.
Date: March 9, 1960
Creator: Beard, S. J. & Oberg, G. C.
Partner: UNT Libraries Government Documents Department
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Thermal conductivity studies on various calcined ``cold`` waste: Interim report

Description: Accelerated accumulation of high level radioactive wastes has given impetus to the development of safer and more economical waste storage methods. Several processes for converting these wastes to granular or porous-solid form are being investigated. In any waste volume-reduction process containment of the final material in a sealed metal shell is desirable as a precaution against accidental release of radioactive material. While the final waste forms are generally stable, they are, if uncontained, subject to some degree to leaching, volatilization, and dusting caused by fracturing due to thermal stresses. An experimental program is now underway to develop an understanding of the variables in waste systems so that suitable storage containers may be designed. This report covers the first phase of the program, a study of heat transfer properties of self-heating granular solids.
Date: March 11, 1960
Creator: DeMier, W. V.
Partner: UNT Libraries Government Documents Department
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Flux distribution problems at C Reactor

Description: This report discusses an outbreak of ruptures in January and February, 1960, which motivated serious consideration of ail phases of reactor operation so that a combined efforts to reduce rupture potential might be made. Items investigated include mixer location, gas composition control, rod movement, rod configuration, tube power, and the axial flux profile of the reactor.
Date: March 16, 1960
Creator: Chitwood, R. A.
Partner: UNT Libraries Government Documents Department
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