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Multirod (Four Rod) Critical Heat Flux at 1000 PSIA

Description: Technical report describing the four-rod heat flux experiments that are a part of a continuing program of study of the critical heat flux, or burnout phenomenon in order that water cooled reactors can be designed with a maximum of safety and efficiency. During heat transfer with boiling, there is a particular heat flux, for a given set of flow conditions and geometry, above which the nucleate boiling process begins to break down. This breakdown of the nucleate boiling process is known as burno… more
Date: September 1963
Creator: Hench, John E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Maritime Loop Irradiation Program for Savannah I Fuel Post-Irradiation Examination of SI5BM Fuel Assembly

Description: Abstract: A stainless steel clad 9-rod assembly fabricated by The Babcock & Wilcox Company was irradiated in a boiling water loop of the General Electric Test Reactor. A post-irradiation examination revealed no significant dimensional changes on the fuel rods. the results of mass spectrometric analysis made of the pelletized UO2 fuel indicated a maximum burnup of 11,500 MWD/tonne was attained by Rod B-4 during the exposure.An x-ray diffraction examination of an unirradiated fuel sample revealed… more
Date: November 7, 1963
Creator: Mathay, P. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Failure Examinations and Analyses in the High Power Density Program

Description: Summary: The High Power Density Project includes a comprehensive fuel development program which has the objective of developing and demonstrating the performance of a nuclear reactor core having a high power density, long fuel life, and low fabrication cost. The fuel program is made up of two principal tasks. Task 1A consists of irradiation tests in the VBWR of Type 304 stainless steel clad, UO2 pellet type fuel rods fabricated by current commercial processes. Task 1B consists of the investigat… more
Date: September 16, 1963
Creator: Arlt, W. H. & Vandenberg, S. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Two-Phase Pressure Losses Quarterly Progress Report: Sixth Quarter, May 12, 1963 - August 12, 1963

Description: Technical report describing that the pressure drops along 3/4-inch, 1-inch, and 1-1/4 inch straight pipes and across three contraction-expansion inserts in a 1-inch pipe have been measured under both single- and two-phase flow conditions. Pressure was varied from 600 to 1400 psia, flow from 0.25 x 10(6) to 1.66 x 10(6) lb/hr ft, and quality from zero to 90 percent. The single-phase pipe friction factor agrees with the Moody value for smooth pipe. The two-phase friction for horizontal flow shows… more
Date: September 1, 1963
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Program of Two-Phase Flow Investigation Quarterly Report: Second Quarterly Report, July-September, 1963

Description: Task A: Modification and Preparation of Experimental Facility. With the exception of the insulation of modified components, the experimental facility is complete. Insulation will be completed by the end of September. the system has been charged with Refrigerant-22 and preliminary loop performance tests have been completed without the test sections.. Task B: Design and Construction of Test Sections. The stainless steel test section has been prepared complete with end flanges and pressure tap loc… more
Date: September 23, 1963
Creator: Staub, F. W. & Zuber, N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Specific Zirconium Alloy Design Program Quarterly Progress Report: Sixth Quarter, July - September, 1963

Description: Summary: Fundamental studies in support of the alloy design work are complete except for the experimental determination of the diffusion of oxygen in alloy-doped non-stoichiometric ZrO2. Over 100 oxidation runs have now been made on samples of ZrO2 doped with 1 mole percent of the oxides of Al, Y, Fe, Cr, and Ni. The first round testing of 31 alloys is now essentially complete. Analysis of the steam corrosion rate and hydriding raw data taken at 300, 400, and 500 degrees C indicates that Zr-C… more
Date: October 1, 1963
Creator: Klepfer, H. H.; Jaech, John L.; Douglass, D. L. (David Leslie), 1931-; Blood, R. E. & Perrine, H. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Eighth Quarterly Report, July-September 1963

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program. Information is reported on vented fuel production, fuel testing in TREAT, fuel performance evaluation, fast-flux irradiation of fuel, and reactor dynamics and design.
Date: October 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Sixth Quarterly Progress Report, July 1-September 30, 1963

Description: Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The development of pulsed neutron source techniques for large power reactors has led to a new theoretical model recently developed by E. Garelis and J.L. Russell, Jr. The theory is presently based on a bare, one-group model with m-delayed precursors and takes all spatial modes into account. Results indicate, however, that the app… more
Date: October 15, 1963
Creator: Garelis, Edward & Meyer, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 4

Description: The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nucl… more
Date: October 1, 1963
Creator: Sorlie, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transition Boiling Heat Transfer Program; Third Quarterly Progress Report, July - September 1963

Description: Summary: Initial critical heat flux, transition boiling temperature fluctuation, and film boiling coefficient data have been obtained on a two-rod cluster assembly at 1000 psia and 25 to 90 percent steam qualities. A representation showing the range of critical heat flux data is presented. Typical temperature recordings which indicate transition and film boiling behavior are shown. Fabrication of a new high pressure observational test section is nearly complete. An optical table and illuminatio… more
Date: October 1, 1963
Creator: Quinn, E. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High Power Density Development Project: Fourteenth Quarterly Progress Report, July-September 1963

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. The number of assemblies has been reduced to seven as a result of the failure of two pellet fuel assemblies. The average burnup of the group operating as of September 1 is 7500 MWD/T. (2) Task 1B-Fuel Fabrication Development. Assembly. Assembly 12S gave positiv… more
Date: October 1963
Creator: Holladay, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Controlled-Environment Steam Corrosion Facility

Description: Abstract; Technical report describing a low-flow autoclave system developed for out-of-pile corrosion testing of materials in controlled environment steam up to 500 C. The system has been set up in triplicate to provide for the exposure of various zirconium alloys to steam at 300, 400, and 500 C. The oxygen and hydrogen of the steam were controlled at 25 ppm and 3 ppm, respectively, to simulate the gas conditions from radiolytic water decomposition found in a boiling water reactor. The autocla… more
Date: October 1963
Creator: Nelson, W. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Program Design and Fabrication of Special Assembly 10-L : Compacted Powder Fuel Rods Clad With 0.127-MM Wall Stainless Steel

Description: Technical report describing sixteen fuel rods clad with thin type 304 stainless steel and filled with vibratory compact powder UO2 that were fabricated and incorporated into a bundle for irradiation testing in the VBWR. The UO2 powders were tested for gas content. N2, CO, and H2 were the principal gases evolved by both type of UO2, but the arc-fused UO2 released about ten times as much gas as the Dyna Pak UO2. The amount of gas released was also a function of particle size and temperature. The… more
Date: October 1963
Creator: Ogawa, S. Y. & Williamson, N. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Prediction of Two-Phase Critical Flow Rate

Description: Technical report of a proposal of an analytical model to predict two-phase critical flow rate. The model is based upon thermal equilibrium, a "lumped" treatment of the two-phase velocity (each phase is represented by a single mean velocity), and upon the neglect of frictional and hydrostatic pressure losses. A comparison, of the proposed predictions with available test results and previous analyses shows that: (1) The present model agrees very well with the published test data. (2) In contrast … more
Date: October 1963
Creator: Levy, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design and Fabrication of Pellet Fuel Rods Clad With Thin Wall Stainless Steel

Description: Summary: Stainless steel clad nuclear fuel cycle costs can be reduced to those associated with Zircaloy clad fuel or potentially lower by reducing the thickness of the clad tube wall until performance penalties offset the savings associated with the reduction in parasitic neutron absorption. To demonstrate the feasibility and investigate performance capabilities of thin clad fuel rods for power reactor application an assembly was fabricated with 0.0127 cm (5 mil) thick stainless steel cladding … more
Date: February 1964
Creator: Hoffmann, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Uranium Dioxide Fuel Rod Center Melting Test in the Vallecitos Boiling Water Reactor

Description: Technical report describing that as part of the AEC Fuel Cycle Program, tests are being conducted to evaluate the significance of current fuel design limitations that do not permit the maximum fuel temperature to exceed the melting point of UO2. The reliability of prediction of the fuel rod operating conditions that will cause melting of the UO2 was evaluated by means of a calibration test conducted in the Vallecitos Boiling Water Reactor. Conclusions: (a) The central portion of the 3.15-cm dia… more
Date: November 15, 1963
Creator: Williamson, H. E. & Hoffmann, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of UO2 Grain Growth Data From "Out of Pile" Experiments

Description: Summary: Data on equlaxed UO2 grain growth from "out of pile" experiments have been gathered from all known sources and analyzed to determine the relationship between the grain size developed and annealing temperature and between grain size and the time at temperature. On the basis of the analysis, an equation relating gain size to time and temperate has been selected that appears to best describe the data considered as a whole. The coefficients in this grain growth equation have been evaluated… more
Date: November 1963
Creator: Lyons, M. F.; Coplin, D. H. & Weidenbaum, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Safety and Fuel Cycle Economics Considerations for Fast Reactors

Description: Abstract: A core design study of a 10 Mwe fast ceramic reactor is presented. Local reactivity coefficients, safety criteria, accident analyses, and economics are considered. An attempt is made to find a new balance of characteristics by purely geometric devices, i.e., by exploring the sodium : fuel ratio and varying the height : diameter ratio of the core. The use of BeO in the core was also investigated.
Date: November 11, 1963
Creator: Cohen, K. P.; Greebler, P.; McNelly, M. J.; Murphy, P. M.; Sherer, D. B. & Zebroski, E. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Seventeenth Quarter, August-October 1963

Description: From introduction: "This is the seventeenth 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: November 15, 1963
Creator: Flock, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Influence of the Doppler Effect on the Meltdown Accident

Description: The influence of the Doppler effect in the core disassembly process following a meltdown accident is examined with a Bethe-Tait type model in which the Doppler effect, as well as core disassembly, is considered in the reactor shutdown process. It is shown that a strong negative Doppler effect can radically reduce the explosive energy release in such an accident. (auth)
Date: November 18, 1963
Creator: Wolfe, B.; Friedman, N. & Riley, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Applications of Strain Cycling Considerations to Superheat Fuel Design

Description: A potential performance limitation of superheat fuel is the susceptibility of the fuel cladding to low cycle fatigue failure. Two simplified analytical methods are presented to estimate the cyclic lifetime of circular superheat fuel cladding. One failure relation is based on a displacement method. The other failure relation is based on a stress method. These relations were compared with data from the literature, and with data involving damage obtained by Reynolds. A recommended design procedur… more
Date: June 1963
Creator: Rieger, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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