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EGCR Lattice Radial and Angular Power Distribution

Description: One of the problems encountered in the design of the EGCR has been the possibility of bowing in the outer six rods of the seven rod cluster. The power distribution in an outer rod is asymmetrical with respect to the center of the rod. This causes a variation in the cladding temperature, and might result in unven thermal expansion, or bowing.
Date: January 19, 1960
Creator: Nichols, P. F.
Partner: UNT Libraries Government Documents Department
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RADIOLOGICAL HAZARDS FROM RUPTURE OF THE SECONDARY COOLANT SYSTEM OF THE 10 Mw ESCR

Description: The hazards study was made to determine the radiation level from the secondary sodium lines of the l0-Mw ESCR, and to evaluate the corresponding radioactive concentration in the secondary loop and the maximum permissible effective activation flux in the intermediate heat exchanger. The results are presented graphicallyn the radiation level from the coolant lines during normal operation as a function of line diameter and Na/sup 4/ concentration; the effective thermal neutron activation flux leve… more
Date: January 19, 1960
Creator: Piccot, A.R.
Partner: UNT Libraries Government Documents Department
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Examination of a Nonregenerative Heat Exchanger From the u.s.s. Nautilus (Ssn-571)

Description: Selected components from a staianless steel nonregenerative heat exchanger removed from the U.S.S. Nautilus (SSN571) have been examined for evidence of stress-corrosion cracking. The examination was conducted on three baffle plates, all primary-face seal welds, and the tubes and the surrounding tube sheets of 7 out of a total of 35 tubes. Maximum operating temperature of the heat exchanger was 260 ction prod- F for the inlet primary water and 164 ction prod- F for the exit secondary water. Chlo… more
Date: February 19, 1960
Creator: Berry, W. E.; Stewart, O. M. & Fink, F. W.
Partner: UNT Libraries Government Documents Department
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An Industrial Gamma Irradiator for Medical Supplies

Description: From foreword: This report presents the preliminary design of an industrial gamma irradiator for the sterilization of medical supplies.
Date: February 19, 1960
Creator: Frankfort, J. Harry; Haram, S. & Wallach, S.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly record report, January 1960

Description: This document details activities of the irradiation processing department during the month of January 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: February 19, 1960
Partner: UNT Libraries Government Documents Department
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An IBM 704 Subroutine for Trapezoidal Integration With Controller Error (Trice)

Description: A description of the IBM-704 subroutineTRICE, which evaluates a single integral by means of the trapezoidal rule approximation is given. In the calculational procedure, the integration step is halved until the desired degree of convergence is reached or until a preset maximum number of steps is exceeded. A maximum of ten different integrands may be used in any one calling program. The subroutine is written in FORTRAN. (auth)
Date: April 19, 1960
Creator: Nestor, C. S.
Partner: UNT Libraries Government Documents Department
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Judgment analysis of comparative C-64-F and X-8001-F alloy canned fuel element performance

Description: Fuel element component procurement requires a considerable lead time (three to four months after design is completed). Collection of data and statistical analyses to evaluate the performance of these components takes even longer. There is often reluctance to disturb the status quo in these matters without engineering recommendations; these are usually not given until the parameters are defined quantitatively with a high statistical level of significance. The purpose of this analysis is to take … more
Date: April 19, 1960
Creator: Brown, R. W.
Partner: UNT Libraries Government Documents Department
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The Neptune Event--a Nuclear Explosive Cratering Experiment

Description: The Neptune device was detonated underground in a room approximately 12 x 17 x 10 ft, at the end of a hooked drift. The yield was 115 plus or minus 15 tons. The shot and its effects are described and the major contributions of the data to the theory and prediction of cratering phenomenology are indicated. (W.D.M.)
Date: April 19, 1960
Creator: Shelton, A V; Nordyke, M D & Goeckermann, R H
Partner: UNT Libraries Government Documents Department
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Ultrasonic Cleaning of Fuel Elements Components

Description: Ultrasonic cleaning uses high-frequency sound waves to induce cavitation within a cleaning, medium. During cavitation, millions of small bubbles form and collapse, resulting in agitation proportional to the energy put into the solution. The making and breaking of these bubbles produce the scrubbing action associated with ultrasonic cleaning.
Date: April 19, 1960
Creator: Strand, C. A.
Partner: UNT Libraries Government Documents Department
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Fission Product Distribution in ORR Fuel Elements

Description: The gamma rays emitted by ORR fuel elements and by the fuel section of shim rods are measured as a function of position along the elements with a very small graphite ionization chamber. Comparison of the fuel burnup calculated from the gamma measurements and by the flux-time method shows good agreement. This means that the gammaray distribution measurements could be a good method of determining the U/sup 235/ consumption in fuel elements. Distributions of the macroscopic absorption cross sectio… more
Date: May 19, 1960
Creator: Colomb, A. L.
Partner: UNT Libraries Government Documents Department
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IBM-704 CODES FOR PREDICTING THE RESPONSE OF GAMMA-RAY SCINTILLATION COUNTERS

Description: A manual for Operating several codes for an IBM-704 to calculate the pulse-heat response functions for gamma-ray scintiliation counters is presented. Using . the Monte Carlo method of computation, the codes will calculate the pulse-heat response function of xylene, Csl, or Nal counters of various geometrical configurations with cylindrical symmetry. Various monoenergetic source configurations are possible with a maximum source energy of 10.22 Mev. (auth)
Date: May 19, 1960
Creator: Zerby, C D & Moran, H S
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Report: April 1960

Description: This document details activities of the irradiation processing department during the month of April, 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: May 19, 1960
Partner: UNT Libraries Government Documents Department
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Quarterly Report Technology of Non-Production Reactor Fuels Processing Budget Activity 2790

Description: This report summarizes the research and development work carried out during December, 1959, and January and February, 1960, for Budget Activity 2790 - Separations Development for Non-Production Reactors. The major effort on Activity 2790 has been completed. Current efforts on the remaining problem areas will enable Hanford to begin reprocessing fuel elements from power reactors which employ depleted or slightly enriched uranium fuels in July, 1962.
Date: May 19, 1960
Creator: Cooper, V. R.
Partner: UNT Libraries Government Documents Department
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APPR-1 STARTUP ANALYSIS

Description: The Army Package Power Reactor (APPR-1) control system was analyzed to find its response to a startup accident. The system was found to be adequate, at 0.086%/sec rod withdrawal, for operation of at least twice the rated power. (C.J.G.)
Date: July 19, 1960
Creator: Stone, R. S.
Partner: UNT Libraries Government Documents Department
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Longitudinal flux flattening

Description: To date a great deal of emphasis has been placed on flattening the side-to-side and top-to-bottom flux distribution with only minor effort to improve the front-to-rear distribution. Minor variations in the front-to-rear distribution have been achieved by horizontal control rod and Supplemental control positioning. It has-been reasonably well established that the rupture potential for one tube charge increases markedly with higher specific power and temperature; thus there is a great deal of inc… more
Date: July 19, 1960
Creator: Stiede, W. L.
Partner: UNT Libraries Government Documents Department
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Radiometallurgical examination of 1.47 enriched I&E fuel elements for PT-IP-247-A

Description: Under the conditions of PT-IP-247-A, four columns of self-supported and four columns of rib-supported I&E 1.47% enriched fuel elements were irradiated to determine their relative performance under severe operating conditions. Four of the self-supported and two of the rib-supported control elements were received for nation. The two rib-supported control pieces, which were classified as ``near failures`` had received average exposures of 353 and 359 MWD/T at average specific power levels of 91 an… more
Date: July 19, 1960
Creator: Teats, R.
Partner: UNT Libraries Government Documents Department
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Spectrophotometric studies of solutions at elevated temperatures and pressures: status and program for FY1961 and part of FY 1962

Description: A program was initiated on the spectrophotometric study of aqueous solution chemistry. The goal is operation at temperatures up to at least 330 deg C and at pressures up to 200 atm, and to near the critical point if this appears to be feasible. A spectrometer capable of operation under these extreme conditions is being designed. (W.L.H.)
Date: July 19, 1960
Creator: Biggers, R. E. & Chilton, J. M.
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part I. Summary of Technical and Economic Status as of 1960. Heavy Water-Moderated Power Reactors

Description: A revision of section 8 of TID-8516, Part I, is presented. The reactor concept which is presented is a change from the former design, a pressurized- pressure vessel-indirect cycle plant to a boiling-pressure tubedirect cycle plant. A description of the plant and a summary of characteristics for the 110- and 325- Mwe systems are given. (J.R.D.)
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part II. Economic Potential and Development Program. Heavy Water-Moderated Power Reactor

Description: The reactor design which forms the base for the current economic status of D/sub 2/O-moderated reactors was estimated from developments in several reactor programs. However, since a heavy water-moderated reactor was not operated on natural U fuel at power reactor conditions, considerable improvement from this current status can be foreseen. A summary of improvements is presented concerning the concept which would result solely from operation of succeeding generation plants without a parallel de… more
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part III. Status Report on Large (100 and 300 MWe) Heavy Water-Moderated Power Reactors--as of 1960

Description: An evaluation of 300- and 100-Mwe power plants was conducted using ground rules prescribed by the USAEC for this study. Costs corresponding to two average discharged fuel burnups are: 8.6 mills/kwh (8500 Mwd/ metric ton) and 8.8 mills/kwh (7500 Mwd/metric ton) for the 300-Mw plant. Costs for the 100 Mw plant are 14.7 mills/kwh for an average discharged fuel burnup of 6010 Mwd/metric ton. Estimates of future potential indicate that the 300 Mw/sub 3/ (8500 Mwd/metric ton) plant could produce powe… more
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Partner: UNT Libraries Government Documents Department
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Advanced Once-Through Steam Generator for Sodium Application

Description: Preliminary design calculations were performed for a once-through type steam generator and reheater for advanced sodium power plants in the 300-Mwe range. Parameters and performance data are presented. (D.L.C.)
Date: September 19, 1960
Creator: Terpe, G.R.
Partner: UNT Libraries Government Documents Department
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[Aerosol Generator Design] : Letter Report

Description: The following report provides information on an aerosol generator fit to produce fine particles by a vaporization-condensation technique. Included is a diagram of the essential components of the generator.
Date: October 19, 1960
Creator: Rosinski, John & Stockham, John D.
Partner: UNT Libraries Government Documents Department
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Estimation of Reaction and Heat Release Rates for Graphite Oxidation

Description: A literature study has been made of rates for the reaction of oxygen with high-purity artificial graphite. Values from a number of sources have been expressed on a common basis which provides approximate correction for the retarding effects of oxygen diffusion in the graphite pores. The corrected rates can be correlated by the equation k = 7.24 x 10^9 exp (-22 100/T), where k has units of weight fraction oxidized per hour and T as in °K. Effects of oxygen concentration, solid and gas-phase cont… more
Date: October 19, 1960
Creator: Prados, John W.
Partner: UNT Libraries Government Documents Department
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