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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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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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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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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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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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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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Control of radio-iodine emissions from the separations plants

Description: The release of radio-iodine from the irradiated uranium during dissolution, and the emission of a portion of this radio-iodine to the environs via the separations plant stacks continues to be a problem in spite of the expenditure of several million dollars for equipment designed to remove the radio-iodine from the gaseous wastes. This report discusses the control of the radio-iodine emissions from the hanford separation processes.(JL)
Date: December 19, 1960
Partner: UNT Libraries Government Documents Department
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New inlet nozzle assembly: C Reactor

Description: The use of self-supported fuel elements in ribless Zircaloy-2 tubes at C-Reactor requires some inlet nozzle modification to allow charging of the larger overall diameter fuel pieces. A new nozzle assembly has been developed (by Equipment Development Operation -- IPD) which will allow use of the new fuel pieces and at the same time increase the reliability of the header-to-tube piping and reduce pumping power losses. Flow test data were requested for the new assembly and the results of these tes… more
Date: October 19, 1960
Creator: Calkin, J. F.
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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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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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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Discussion-preliminary review of the safety aspects of the crossunder line, Project CG-884. Volume 1

Description: In order to reduce both charge-discharge shutdown time and the number of manhours of radiation exposure, Project CGI-884 is being completed at the B, D, DR, F and R Reactors. This consists essentially of installing a large drain line at the bottom of one rear reactor riser. This drain line passes to a control valve and then to the effluent line beyond the downcomer. This system by-passes the crossover downcomer part of the effluent system and eliminates the need for intermittent rear crossheade… more
Date: December 19, 1960
Creator: Jones, S. S.
Partner: UNT Libraries Government Documents Department
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Production test IP-363-A irradiation of ZR-2 jacketed enriched single tube fuel elements in the KER loops

Description: The objective of this production test is to evaluate the behavior during irradiation of nominally 1.739 inch OD., 1.074 inch ID., Zircaloy-2 jacketed single tube fuel elements with brazed end closures at operating conditions somewhat more severe than those expected for N Reactor fuel element outer tubes. Enriched single tube elements with brazed end closures and modified fuel element supports are authorized for irradiation in the KEG loops to an exposure no higher than 4000 MWD/T. A typical loa… more
Date: October 19, 1960
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Causes of reactor shutdowns

Description: The purpose of this report is to present an analysis of causes of reactor shutdown as a support to various engineering programs presently under study. Continuing measurement and correlation of these facts can demonstrate the incentives and the necessity for modifying or changing present concepts in reactor safety and control circuits as reactor power levels are continuously increased.
Date: December 19, 1960
Creator: Deichman, J. L.
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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Feasibility Study of a New Mass Flow System : Quarterly Report No. 2 Covering the Period from September 1 to November 30, 1960

Description: This is the second quarterly report that documents a system of mass flow that can record measurements of homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, additionally considering pressure drops, measuring external to the flow, ruggedness and reliability.
Date: December 19, 1960
Creator: Burgwald, G. M.; Stone, C. A. & Genthe, William K.
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 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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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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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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High Temperature Cladding Alloys for Reactor Applications

Description: The development of several metallic fuei element systems for air-cooled reactors is reviewed, and the hightemperature properties of Type 310 stainless steel and Nichrome V clad fuel elements are discussed. Early work on cladding of Mo is reviewed, and recent developments in ferrous-base alloys and Cr-base alloys as hightemperature cladding materials are presented. (auth)
Date: October 19, 1960
Creator: Collins, J. F. & McGurty, J. A.
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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THE ORIGIN OF LIFE ON EARTH AND ELSEWHERE. II

Description: The synthesis of relatively complex organic molecules by ionizing and radical mechanisms (induced by high energy radiations, ultraviolet and electric discharge) from methane, ammonia, water, and hydrogen is described, both theoretically and experimentally. It is shown that the molecules which tend to be formed under such random conditions are the very ones which today are the common building blocks in the biological reconstruction of organic material. Such molecules are the amino acids, the sim… more
Date: October 19, 1960
Creator: Calvin, Melvin
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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