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THE EFFECT OF PLANT THERMAL EFFICIENCY ON THE COST OF NUCLEAR POWER
Nuclear power cost is plotted versus thermal efficiency. The relationship is not limited to any particular reactor type and is applicable for any reactor system where steam is the working fiuid for the turbogenerator. (T- R.H-)
Neutron Remote Area Monitoring Systems
The following report records measurements and evaluations of fast neutron levels in remote areas monitored by personnel.
Wind-Tunnel Data on the Longitudinal and Lateral-Directional Rotary Derivatives of a Straight-Wing, Research Airplane Configuration at Mach Numbers From 2.5 to 3.5
Memorandum presenting the results of wind-tunnel oscillation tests to measure the rotary derivatives of a research airplane configuration at supersonic speeds. Measurements were made of the damping in yaw, pitch, and roll, the static longitudinal and directional stability derivatives, the effective-dihedral derivative, the rolling moment due to yawing, and the yawing moment due to rolling. The configuration was found to be statistically stable throughout the Mach number range, although its stability was becoming marginal at high angles of attack at Mach number 3.5.
The Prompt Radiations in the Spontaneous Fission of Cf²⁵² (Revised)
Summary: The radiations emitted in the spontaneous fission of Cf²⁵² have been studied. The results in general are in agreement with other similar measurements. An experiment is described which is expected to give the neutron energies and angular distribution in the center-of-mass system of the moving fission fragment when the analysis is completed.
Simulation of Various Accident Considerations for a Merchant-Ship Pressurized-Water Reactor
A study was conducted on the safety aspects of foreseeable accident types in connection with the Nuclear Merchant Ship Reactor program. Four accidents have been selected for analysis by analog simulation techniques: continuous rod withdrawal, startup, loss of coolant flow, and cold-water insertion. The simulation of the reactor only was required for these situations because the effects of the accidents would be completed in less than one primary- coolant loop time. The external control system was ignored, and only the effects of the negative reactivity cocfficients were considered in the natural shutdown of the plant. Three phases of operation were considered in these analyses: operation with no safety system, high-flux scram, and period scram. The programs involved the variations of the scram parameters and the reactor temperature coefficients over the range of possible values for this reactor power plant. Results indicate that the inherent stabliity of the reactor system is sufficient to attenuate the power excursions resulting from the first three accidents. In the coldwater accident, if the difference in loop temperatures is on the order of 300 deg F, scram is necessary to limit the power excursion. (auth)
Volatility Studies of Some Fission Product Fluorides
A preliminary study of the volatility behavior of molybdenum indicated that MoF/sub 5/ was converted to MoF/sub 6/ by F/sub 2/; MoF/sub 6/ and Tc fluoride are absorbed on NaF at 100; technetium fluoride is more strongly held than molybdenum fluoride on NaF; MoF/sub 6/ may not be completely trapped by a dry ice trap. The behavior of volatile fission product fluorides was such that (a) Ru and Nb fluorides were volatile from fused salts during fluorination, (b) Mo and technetium were not volatile during hydrofluorination but were in excess F/ sub 2/> 100 deg C(auth).
Forces Between Nucleons And Antinucleons
Existing experimental information about the nucleon-anitnucleon interaction is reviewed, and a description is given of a theoretical model, based on the Yukawa theory, which seems able to explain the experimental results.
Vinyl Coating of Graphite Plates for Ultrasonic Inspection
A process has been developed for application of a thin, adherent vinyi plastic coating to graphite plates to prevent absorption of coupling fluids'' used in ultrasonic inspection. The plates are preheated and dipped mechanically in a fluid plastisol, and the resulting coating is fused in an infra-red heater. No significant attenuation of ultrasonic impulse results from presence of the coating. After inspection, the vinyl sheath may be easily stripped from the plate. (auth)
Amendment No. 2 To Preliminary Hazards Summary Report For The Dresden Nuclear Power Station
This report is the second amendment to the Preliminary Hazards Summary Report for the Dresden Nuclear Power Station (GEAP-1044) submitted to the United States Atomic Energy Commission on September 3, 1957.
Reactor Components Study
Reactor operating conditions are formally established to conserve pile life. A major part of the 2000 Research and Development effort is oriented to develop fundamental information required to properly establish these limiting operating conditions. This report reviews the current condition of reactor components believed important to continued productive life of the reactors and discusses the current status of technologies important in estimating the future productive life of the reactor complex. These evaluations are conducted continuously and this report is one of a series of status reports.
In-reactor corrosion of X-8001 and 1245 aluminum: Analysis of data from PT IP-42A
Failures of standard fuel element jackets (1245 aluminum alloy) after relatively short Hanford reactor exposures are occurring at high reactor power levels. Metallographic examination of fuel element jackets from short exposure ruptures shows the cause of failure to be rapid intergranular corrosion. This type of attack has been reproduced in laboratory tests by exposure to water at temperatures above 200 C, or to steam at temperatures higher than 300 C. Flow disruptions due to misalignment of the fuel elements within the reactor process tube, worn tube ribs, etc., are believed to cause the high local jacket temperatures necessary for the occurrence of intergranular corrosion.
Nuclear Gas Engine
A preliminary design study of the nuclear gas engine, consisting of a gas-cooled reactor directly coupled to a reciprocating engine, is presented. The principles of operation of the proposed gas engine are outlined and typical variations anre discussed. The nuclear gas engine is compared with other reciprocating engines and air compressors. A comparison between the ideal and actual cycles is made, with particular attention given to pumping, heat, and other losses to be expected. The applications and development of the nuclear gas engine are discussed. (W.D.M.)
Theoretical Rocket Performance of JP-4 Fuel with Several Fluorine-Oxygen Mixtures Assuming Equilibrium Composition
"Theoretical rocket performance for equilibrium composition during expansion was calculated for JP-4 fuel with several fluorine-oxygen mixtures for a range of pressure ratios and oxidant-fuel ratios. The parameters included are specific impulse, combustion-chamber temperature, nozzle-exit temperature, molecular weight, characteristic velocity, coefficient of thrust, ratio of nozzle-exit area to throat area, specific heat at constant pressure, isentropic exponent, viscosity, thermal conductivity, and equilibrium gas compositions. A correlation is given for the effect of chamber pressure on several of the parameters" (p. 1).
Elevated-Temperature Combined Stress-Rupture Plus Fatigue Strength of Waspaloy Having Different Aging Treatments and/or Molybdenum Contents
Report presenting an investigation to determine if the combined stress-rupture plus fatigue strengths of three groups of Waspaloy with different aging treatments and/or molybdenum contents could be correlated with their stress-rupture ductilities and notch-rupture strengths. Waspaloy is of interest as a gas turbine-bucket alloy because it has low strategic material content and relatively good stress-rupture properties. Results regarding metallurgical evaluation of the failed specimens are also provided.
Revised model to describe side rupture data
It has been noted on occasion that the side rupture rate at lower exposure is higher than one would expect in order to be consistent with the mathematical model (Weibull curve) used describe the rupture data. This has apparently been due to a few ruptures occurring at exposures lower than one would anticipate on the basis of the model. Restricting themselves to fuel elements irradiated under similar conditions of power and temperature, it is difficult to assert that these ruptures are anomalous with respect to the model used since there are so few ruptures involved. For this reason, some means of combining data was called for in order to see whether or not at least some of these low exposure ruptures were inconsistent with the model, and, if so, to revise the model in order to better describe side rupture performance. In this report, the results of an analysis of side failure data for failures covered in a previous report are given. Also included is a discussion of possible implications derived from recognition of the existence of this revised model.
Arc Calcination of Thorium Oxide
An over-all description of the background material on the use of electrical arcs for heating of powders is presented as well as a summary of experimental studies on the arc calcination of thoria. Favorable results have been indicated both with heating thoria powder in an arc heated gas and with thoria formed into a consumable electrode. Use of a consumable electrode produces thoria particles 0.1 to 0.01 mu in diameter. It is recommended that additional electrodes be fabricated and further arc calcination tests be run to produce a quantity of product sufficient for evaluation. (auth)
Operating conditions for Pt IP-205-A, irradiation of Zircaloy-2 jacketed rod-and-tube elements in the KER Loops
No Description Available.
Natural Steam and Geothermal Power Generation : [bibliography]
The following document is a bibliography containing a collection of documents discussing natural steam and geothermal power generation.
Remote Maintenance Experimental Work on a Reactor System Pump
An experimentally determined evaluation of standardremote-handling equipment applied to the problems associated with remote maintenance of a typical reactor system component is presented It is comcluded that commercially available equipment can be used and that a good techmician can rapidly learn the use of manipulators required in remote maintenance. The use of closed circuit television in maintenance is possible; however, further development of radiation- resistant equipment is required. (j.R.D.)
Review of the Corrosion Product Radioactivity Program at the Army Package Power Reactor : Alco R & D report
Abstract: An analysis and a summary are.given of the radioactivity buildup program at the Army Package Power Reactor during the last nine months. · Due to the wide fluctuation of water and crud results, only general interpretations can be made with this data. Metal test coupon data indicate a substantially greater buildup on Croloy 16-1 metal than on Type 304 stainless steel. Coupled with the decreased ability to remove the radioactivity buildup on Croloy 16-1 by conventional descaling techniques, the implication is that this metal might pose a serious problem for use as steam generator material. It was emphasized, however, that results to date ae only preliminary and extensive additional experimentation would be required to reach more definite conclusions.
Effect of fuel-orifice diameter on performance of heptane-oxygen rocket-engines
A study of the effect of fuel-orifice diameter on the performance of heptane-oxygen rocket engines with single-element injectors. Five engines with a range of thrust were tested with parallel-sheet, triplet, and parallel-jet injectors. Decreasing the fuel-orifice diameter was found to increase the performance for a fixed chamber length. Results regarding injector performance and a comparison of experimental and analytical results are provided.
Redox accountability test program: Initial results
This report details initial results of a large scale accountability test program which was recently carried out in the Redox Facility. The test, as originally planned which was to consist of the complete processing (no inventory-clean plant basis) of about 55 tons of selected metal in conjunction with an extensive analytical, sampling, and volume measurement program. With the exception of two incidents, the processing requirements (minimum inventory and measurement of all material) necessary to the success of the test, were met. The two incidents which increase the uncertainties associated with some of the material balance values obtained were: the discharge of an estimated 700 pounds of uranium to the floor in a transfer from F-5 to F-4 due tot he improper installation of the F-5 to F-4 transfer line (jumper) and the discovery of a large accumulation of plutonium ({approximately} 15 kg) in the L-2 stripping tower after completion of the test run.
A Preliminary Study of the Effect of Boric Oxide Deposits on the Performance of Two Selected Turbine Stator-Blade Shapes
Report discussing testing on the performance of two stator-blade shapes with and without boric oxide deposits. The deposits were found to cause total pressure losses and decreases in the blade-exit flow angle. Information about the cascade throat area, boundary-layer momentum thickness, total pressure ratio, and exit flow angle and tangential component of velocity is provided.
A preliminary study of the effect of boric oxide deposits on the performance of two selected turbine stator-blade shapes
Report presenting the performance of two stator-blade shapes with and without boric oxide deposits, which was determined in a two-dimensional cascade. The differences between the blades were the amount of curvature and suction-surface diffusion downstream of the throat. Results regarding the cascade throat area, boundary-layer momentum thickness, total-pressure ratio, and exit flow angle and tangential component of velocity.
Exploratory Investigation of Performance of Experimental Fuel-Rich Hydrogen Combustion System
Memorandum presenting an exploratory investigation conducted to determine the performance characteristics of a fuel-rich hydrogen combustor; in addition, the performance of an afterburner operating with the fuel-rich exhaust mixture was evaluated. Results regarding performance of the fuel-rich combustor, afterburner performance, and resonating combustion are provided.
Summer Quarter, 1958, Co-Op Report
process and fluidized bed reactor is reported. Work done on cleanup of mercury from the Metallex process is also described. (J.R.D.)
Biology and Medicine Semiannual Report for October 1957 Through March 1958
Data are presented from the following studies: the radiation chemistry of pepsin, gelatin, methanol, benzene, and hexanes; the effects of irradiation of the pituitary in advanced cancer using high-energy particles from the 184-inch cyclotron; applications of ion beams in biological studies; the metabolism of strontium-90 and its relation to calcium metabolism in rats; hematological effects of low-level radiation doses in man; the influence of diet on serum lipoproteins; development of simplified methods for the analysis of blood serum for lipid content; tracer studies employing iron59 of red blood cell production and destruction and iron metabolism in a wide variety of blood disorders; tracer studies on heart function and blood circulation employing I/sup 131/; applications of C/sup 14/ in studies of leukocyte formation from which it was concluded that peripheral neutrophils have a 2-day life span, large lyphocytes a life span of 2 to 3 days, and small lyphocytes a life span of between 8 and 14 days; tracer studies employing P/sup 32/ in studies of the phagocytic action of cells of the reticuloendothelial system; factors regulating the volume of the body fluids; and development of a method for determining estrogen concentration in urine. Radiation protection activities are summarized. Lists are included of reports issued and papers published during the period. (For preceding period see UCRL-8031.J (C.H.)
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