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In-Core Instrumentation Development Program Quarterly Progress Report June - September 1963

Description: Introduction: The objective of Project Agreement 22 is to determine the feasibility of covering the complete reactor neutron flux start range from 10(3) - 5 x 10(13) nv by using in-core chambers. The counting mode of operating will be used at low neutron fluxes and the root mean square voltage fluctuation mode will be used at high neutron flux levels. Experiments have been run utilizing various ion chambers, gases, gas pressures, voltage, and cables to measure sensitivities and range operating … more
Date: October 1963
Creator: DuBridge, R. A.
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report September - December 1963

Description: Introduction: The objective of Project Agreement 22 is to determine the feasibility of using in-core ion chambers to cover the complete reactor neutron flux startup range from 10(4) -5 - 10(13) nv using in-core ion chambers. The counting mode of operation will be used at low neutron flux levels and the RMS voltage fluctuation mode (Campbell Theorem) will be used at high neutron flux levels. The June-September Progress Report (GEAP-4386) shows how the RMS voltage mode can be used, discusses c… more
Date: January 1964
Creator: DuBridge, R. A.
Partner: UNT Libraries Government Documents Department
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Mechanical, Fluid Flow, and Heat Transfer Out-Of-Pile Tests on EVESR MKI Prototype Fuel Bundle

Description: Summary: An EVESR MKI prototype fuel bundle was fully instrumented and operated intermittently for a 5-month period at the Pacific Gas and Electric Company’s Moss Landing Power Station. The vessel was operated up to 1000 psi with steam flows from 3000 to 26,600 lb/h, and steam inlet temperatures up to 825 degrees F. Data was recorded for blowout, vibration, flow distribution, heat transfer and pressure drop. The mechanical integrity of the fuel bundle, riser, and jumper system was satisfact… more
Date: February 1964
Creator: Polomik, E. E.; Fritz, J. R. & Ianni, P. W.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Eighteenth Quarter, November, 1963-January, 1964

Description: From introduction: "This is the eighteenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Date: February 15, 1964
Creator: Flock, W. L. & Imhoff, D. H.
Partner: UNT Libraries Government Documents Department
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Preoperational Power Stability Analysis of the Consumers Big Rock Point Plant

Description: Summary: An analytical study of the stability of the Big Rock Nuclear Reactor has been performed for the plant as built, and supplements a previous design stability study. The plant has been determined by this analysis to be very stable under every mode of operation anticipated during Phase I of the development program testing. Even under conservative assumptions of system parameters the minimum calculated gain and phase margins do not go below 13.0 db and 46 degrees, respectively. (Nor are … more
Date: February 1964
Creator: Case, J. M.
Partner: UNT Libraries Government Documents Department
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Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: July 1 - September 30, 1963

Description: A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. Quarterly progress: The densitometry procedure (for measurement of alpha autoradiographs of fuel pellets) has been modified to eliminate the need for a second emulsion. The existence of a problem of latent image fading and non-reciprocity of … more
Date: October 15, 1963
Creator: Robkin, M. A.
Partner: UNT Libraries Government Documents Department
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A Program of Two-Phase Flow Investigation Quarterly Report: Fourth Quarterly Report, January-March, 1964

Description: Summary: The design, construction and assembly of all components were completed during the first contract year previous to December 1963. These efforts, defined by Tasks A-F, are document in (1), (2), and (3). Brief summaries of these completed efforts are given in the introduction to each of the tasks in the text of this report. The digest given below covers only the shakedown and analysis work carried out in the fourth quarter of the first contract year. Task G Shakedown Tests. The photo… more
Date: March 16, 1964
Creator: Staub, F. W. & Zuber, N.
Partner: UNT Libraries Government Documents Department
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Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Tenth Quarterly Report, January-March 1964

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program. Information is reported on vented fuel production, transient testing of fuel, fuel performance evaluation, fast-flux irradiation of fuel, and reactor physics and core analysis.
Date: April 1964
Creator: Breizy, C. E.
Partner: UNT Libraries Government Documents Department
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Transition and Film Boiling Data at 600, 1000, and 1400 PSIA in Forced Convection Heat Transfer to Water

Description: Summary: Data were obtained in a two-road test section which consisted of two 7/16-inch diameter heater rods inside a roughly rectangular flow area. The heated length of the rods was 30 inches, with a 15-inch unheated calming length preceding it. Heater wall temperatures were recorded while the heater tubes were trans-versing the critical heat flux and transition boiling; these temperatures were used to calculate heat transfer coefficients. The following general results were obtaining: (a)… more
Date: March 1964
Creator: Hench, J. E.
Partner: UNT Libraries Government Documents Department
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Transition Boiling Heat Transfer Program; Fifth Quarterly Progress Report, January - March 1964

Description: Summary: Tests with the two-rod assembly were performed with liquid film trippers attached to the unheated wall, and a variation in rod spacing. Experimental data and improved high-speed motion pictures have been obtained of transition boiling behavior. The changes of the local heat transfer process between nucleate and film boiling can be readily distinguished i the motion pictures. Observational test performed with very short fins on the heated surface resulted in essentially eliminating … more
Date: April 1, 1964
Creator: Quinn, E. P.
Partner: UNT Libraries Government Documents Department
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Transition Boiling Heat Transfer Program; Fourth Quarterly Progress Report, October - December 1963

Description: Summary: Heat transfer tests employing the two-rod test section without film tripping devices have been completed. Representations defining critical heat flux, transition boiling and film boiling behavior at high pressures and over a steam quality range of 25 to 90 percent are shown. Fabrication of a new observational test section was completed and initial test results with high-speed motion pictures were obtained. A test loop instability which was found to affect transition boiling behavio… more
Date: January 1, 1964
Creator: Quinn, E. P.
Partner: UNT Libraries Government Documents Department
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Transition Boiling Heat Transfer Program; Sixth Quarterly Progress Report, April - June 1964

Description: Summary: Transition boiling data was taken with an improved flow loop, to explore the influence of loop characteristics on rod temperature fluctuations the transition region was found to be much smaller than for comparable conditions with a different loop. Also the amplitude, and frequency of the temperature oscillations, were significantly less than before. These results indicate that loop characteristic and flow disturbance parameters play a prominent part in governing the transition tempe… more
Date: July 1, 1964
Creator: Quinn, E. P.
Partner: UNT Libraries Government Documents Department
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Two-Phase Pressure Losses Quarterly Progress Report: Eighth Quarter, November 12, 1963 - February 11, 1964

Description: Technical report describing that voids were measured in a ½-inch by 1-3/4-inch channel with the S-1 insert (B(0)/B(1) = 0.4, L(0) = 0.1 inch), at 2 inches ahead of the insert (position A), ½-inch past the insert (position B), 5 inches past (position C), and 12 inches past (position D). The conditions were: P – 1000 psia, G = 1.00 x 10(6) lb/h-ft(2), and x = 18.8 percent. Average void and void distribution at position A are the same as for flow in a straight channel. Void distribution at posi… more
Date: March 1, 1964
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
Partner: UNT Libraries Government Documents Department
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High Power Density Development Project: Sixteenth Quarterly Progress Report, January-March 1964

Description: Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC. Five tasks are in progress: (1) Task 1A-High Power Density Fuel Development, (2) Task 1B-Fuel Fabrication Development. Assembly, (3) Task II-Stability, Heat Transfer and Fluid Flow, (4) Task III-Physics Development, and (5) Task IV-Co-Ordination and Test Planning.
Date: April 1, 1964
Creator: Holladay, R. L.
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report January - March 1964

Description: The objective of Project Agreement 22 is to determine the feasibility of using in-core ion chambers to cover the complete reactor neutron flux startup range from 10(4) -5 - 10(13) nv using in-core ion chambers. This technical report discusses the following topics: low versus high cable termination impedance, amplifier considerations, noise considerations, gas and pressure selection, cable selection, effect of gamma, effect of temperature, and remaining problems.
Date: April 1964
Creator: DuBridge, R. A.
Partner: UNT Libraries Government Documents Department
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The Development of a Scheduling Computer For The Big Rock Plant

Description: The basic work for development of a scheduling computer for the Consumers' Big Rock Plant is outlined in this report. The computer's purpose is to make feasible higher power densities by operation closer to fuel element burnout limits, and to maximize fuel burnup.
Date: 1961
Creator: Beckjord, Eric S.
Partner: UNT Libraries Government Documents Department
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Pressure Drop of Multi-Rod Elements With Helical Spring Spacers

Description: The pressure drop of a new fuel element design concept of spacing rods by means of helical wire springs was investigated experimentally and analytically.
Date: June 1961
Creator: Quinn, E. P.
Partner: UNT Libraries Government Documents Department
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High Power Density Development Project Fourth Quarterly Progress Report : January - March 1961

Description: The fourth quarter of effort applied to the Consumers R & D Program is summarized in the following: high power density fuel development, fuel fabrication development, stability, heat transfer and fluid flow, physics development, operation planning and test coordination.
Date: April 1, 1961
Creator: Holland, L. K.
Partner: UNT Libraries Government Documents Department
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Erosion Experiments of Powder Compacted Uranium Dioxide Under Dynamic Steam Flow (Preliminary Report)

Description: Experiments were carried out to determine the erosion, oxidation and dimensional characteristics of purposely defected fuel elements containing unsintered UO2 powder prepared by the swaging technique. The experiments were conducted in an out-of-reactor loop under superheat conditions of pressure, temperature, flow velocity and steam chemical composition.
Date: March 21, 1961
Creator: Spalaris, C. N.; Comprelli, F. A. & Siegler, M.
Partner: UNT Libraries Government Documents Department
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High Performance UO2 Program First Quarterly Progress Report: April-June 1961

Description: A better understanding of the maximum operating characteristics that can be achieved with the use of UO2 as a reactor fuel is the primary purpose of this program for Euratom and the Atomic Energy Commission. During this program work will be undertaken in two areas that have been of concern to the reactor core designer for a long time, viz. fission gas release and central melting in fuel rods.
Date: July 1, 1961
Creator: Weidenbaum, B
Partner: UNT Libraries Government Documents Department
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