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The Effect of Fluctuations in the Widths on Neutron Reaction Cross Sections

Description: The general Wigner-Eisenbud theory is used to develop a method of analysis for the cross sections of fissionable nuclei. The method is employed in giving a reasonable description of the low energy cross sections in U/sup 235/. The single level fit for U/sup 235/ is known to be unreasonable. Many level expressions for the cross sections are derived--the only approximation to the general theory being the neglect of all but a small group of resonances. It is shown that regardless of the number or … more
Date: June 1, 1957
Creator: Dresner, Lawrence
Partner: UNT Libraries Government Documents Department
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Operating Instructions for the UNIVAC Program OCUSOL-A : a Modification of the Eyewash Program

Description: The Eyewash program, written by James H. Alexander and Nancy D. Given, provides solutions of reactor criticality problems in spherical geometry by means of the group diffusion method. It employs thirty lethargy groups (plus one thermal group) in nine regions. The input consists principally of specifying the geometrical scaling factor, boundaries and compositions of the various regions, and temperature level. The output includes the value of vc that would render the system critical, the relative… more
Date: June 5, 1957
Creator: Alexander, L. G.; Carrison, D. A.; Roberts, J. T. & Van Norton, R.
Partner: UNT Libraries Government Documents Department
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Two Group Calculations for Flux Distribution and Critical Mass in Clean Cold ORR Cores

Description: A series of two-group calculations has been made on the Oracle for the purpose of obtaining critical-mass and flux distribution data for various ORR core configurations. The 3G3R code of Bate, Einstein, and Kinney was used, together with the RSP code developed by Nelson. This made it possible to obtain results for the three-dimensional case. The results, which are presented graphically, are intended to serve as a guide for the design of experiments until such time as actual measurements are ava… more
Date: March 11, 1958
Creator: Binford, F. T.
Partner: UNT Libraries Government Documents Department
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Evaluation of Coated Al2O3 and Tungsten Carbide Bearing-Journal Assemblies in Westinghouse 100A Pump (Summary of Runs S-96A and S97)

Description: Preliminary results of tests wit the Westinghouse 100A pump indicate that Al2)3 and tungsten carbide coated bearing-journal assemblies prepared by the Linde process are not promising as substitutes for the graphitar-stellite combination. The front Al2O3 assembly failed at start-up with water and both front and rear tungsten carbide assemblies failed after 121 hours with water at 245 C.
Date: May 3, 1957
Creator: Kitzes, A. S. & McLaughlin, C. A.
Partner: UNT Libraries Government Documents Department
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Summary of Corrosion Data for HRT Mockup Operational Period Ending November 5, 1956

Description: The operation of the HRT mockup was on 0.042m UO2SO4, 0.024m H2SO4, and 0.005m CuSO4 at 280 C and 1400 psi pressure. with the O2 content at near 500 ppm. The pump showed bearing wear and high corrosion. The letdown heat exchanger was removed from the mockup and sectioned. The metallographic examination revealed corrosion. Results of corrosion runs on Ti, zircaloy-2, and stainless steel are given.
Date: May 22, 1957
Creator: Wacker, R. E. & Griess, J. C.
Partner: UNT Libraries Government Documents Department
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Final Process Design for Leak Detector System for Special Flanges

Description: The leak detector system consists of one gas pressurized reservoir containing heavy water, a tubing manifold connecting the pressurizer to six separate lines each connected to one of the flanges, tubing lines leading from the second hole on each of three flange pairs (dome and heat exchanger flanges) back into the instrument room, plus required valves and fittings. A schematic diagram of the system in included.
Date: May 29, 1957
Creator: Mason, Edward A. (Edward Allen), 1926-1994
Partner: UNT Libraries Government Documents Department
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Stress Corrosion in the HRT Mockup

Description: Stress corrosion was found in 8 components of the HRT mockup; only of four of these actually shut down the loop. All of the failures have occurred in the high-pressure system of the loop.
Date: May 20, 1957
Creator: Harley, P. H.
Partner: UNT Libraries Government Documents Department
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Effects of Letdown Rates and Oxygen Injection Rates on Xenon Poison Level and Excess Oxygen Concentration in the HRT

Description: Calculations indicate that it is impossible, even at high oxygen injection rates, to insure an excess of oxygen in the HRT fuel solution if the bubble letdown rate is more than 1 or 2 liters per minute. If, on the other hand, no bubbles are allowed to form, a reasonable excess oxygen concentration can be maintained with an oxygen injection rate which would not tax the capacity of the off-gas system. The xenon poison will be reduced to less than 2% by liquid letdown alone, and if an iodine absor… more
Date: May 31, 1957
Creator: Haubenreich, P. N.
Partner: UNT Libraries Government Documents Department
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Low Attack Rates Observed in Toroid Tests with 28 Micron 1600 C Fired ThO2 Spheres

Description: Results of previous toroid tests with 28 micro 1600 fired ThO2 spheres are analyzed. Four possible explanations for the essentially zero attack rates are offered and discussed: peculiar motion of toroids or some unknown wall effect; rotational hydrodynamic forces cushioning the particle impact; the bed was not in suspension and not sliding over the walls of the toroid; round particles are not as erosive to oxide film surface as sharp pointed particles.
Date: May 28, 1957
Creator: Thomas, D. G.
Partner: UNT Libraries Government Documents Department
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In-Reactor Autoclave Corrosion Studies : LITR I. Outline of Methods and Procedures

Description: During the development of in-reactor corrosion experiments three types of bomb designs have been developed for following quantitatively the consumption of oxygen in a bomb which is fabricated from the particular metal under test. The bombs are designed so as to be rocked continuously during their in-reactor exposure, consequently agitating the uranium salt solution contained in the bomb and permitting gentle movement of the solution past metal specimens and other corroding surfaces. The oxygen … more
Date: May 22, 1957
Creator: Warren, K. S. & Davis, R. J.
Partner: UNT Libraries Government Documents Department
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Capillary Flowmeter

Description: The HRT leak detector system consists of four headers each of which are connected on one side to a common supply of pressurized water and on the other side by individual tubing to the ring grooves of approximately twenty flanges. There are two methods of detecting the loss of water that are particularly applicable to the HRT: (1) By the loss of pressure in a constant volume system; (2) By the measurement of flow from a constant pressure system. It was determined to investigate the second method… more
Date: February 20, 1957
Creator: Hise, E. C.
Partner: UNT Libraries Government Documents Department
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Cross Sections for OCUSOL-A Program

Description: The OCUSOL-A program (ORNL-CF-57-6-4) for Univac is a modification of the Eyewash (ORNL-1925) multi-group, multi-region reactor code. The group=energy-lethargy-temperature relationship are given in Table A. The element code numbers are given in Table B. The cross sections now on the sigma-tape are given in tables in the Appendix numbered with the element code number. This technical report explains the bases for choosing the cross sections.
Date: June 11, 1957
Creator: Roberts, J. T. & Alexander, L. G.
Partner: UNT Libraries Government Documents Department
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Effect of Slurry Physical Properties on Heat Exchangers and Pump Characteristics

Description: Design calculations were made for a system consisting of a pump, one hundred feet of pipe, and a heat exchanger to remove 1 Mw of heat from various aqueous thorium oxide slurries. The rheological properties of the slurries were varied over a range of yield stresses from 0 to 1.5 lb/sq ft and of coefficients of rigidity from 1/2 to 2 centipoise. Two different cases were studied: a heat exchanger having fixed axial and radial delta T in which the tube length was allowed to vary and a heat exchang… more
Date: June 10, 1957
Creator: Thomas, D. G.
Partner: UNT Libraries Government Documents Department
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Observed performance of the Fuel Sample Cooler

Description: Measurements of flow rate through the fuel high-pressure system sampler indicate that the average flow rates is about 0.29 gpm (145 lb/hr) plus or minus 50%, which affords an adequate purge of from 12 to 36 volumes through the sample line if the full fifteen minutes of purging is allowed before isolating the sample. The fuel sample cooler was fund to have adequate capacity to reduce the temperature of the fuel solution form about 275 to 70 C, using pre-heated cooling water at 70 C. Uncertaintie… more
Date: June 3, 1957
Creator: Van Winkle, R. & Wiethaup, R. R.
Partner: UNT Libraries Government Documents Department
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Observed Net Heat Loss from the HRT High-Pressure System

Description: An estimate has been obtained of the heat that should be generated in the HRT core in order to hold the system at operating temperature under no-load conditions. This estimate was made by measuring the feed-water rate to the package boiler during an oxygenated water rung. Results are summarized.
Date: June 4, 1957
Creator: Van Winkle, R. & Wiethaup, R. R.
Partner: UNT Libraries Government Documents Department
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The Disposal of Power Reactor Waste Into Deep Wells

Description: For various reasons it is not possible to leave the uranium or other nuclear fuel in a power reactor until all of it has been "burned up" by fission. In the case of liquid fuel (homogeneous) reactors a small part is continuously bled out, purified and returned. In the case of solid fuel reactors, fuel elements are periodically removed, reprocessed and the "unburned" fuel put back into service. In both cases the purification produces wastes which contain radioactive fission products and transura… more
Date: June 13, 1957
Creator: De Laguna, Wallace, 1910- & Blomeke, J. O.
Partner: UNT Libraries Government Documents Department
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HRT Letdown Valves

Description: To supply information about the several letdown valves which have been in HRT service, a typical valve plug examined by the Metallurgy Section confirms the belief that chemical attack on the Stellite #6 was occurring. It appears that most of the corrosion was due to rinse solutions, since this phenomenon has not been noted on letdown valves in the HRT Mockup where over 90% of the operating time has been with UO2SO4 solutions.
Date: June 5, 1957
Creator: Billings, A. M.
Partner: UNT Libraries Government Documents Department
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Chemical Cleaning and Storage of the HRT Steam and Closed Cooling Water Systems

Description: A 10% phosphoric acid solution contain 0.2% "Rodine 45" inhibitor is recommended to be used for the chemical cleaning of the HRT seam and closed colling water systems. Wet storage is recommended for both of these systems. The steam system is to be stored with steam condensate containing 100 ppm hydrazine, and closed cooling water system is to be stored with steam condensate containing 1000 ppm potassium chromate.
Date: June 5, 1957
Creator: McLain, Howard A.
Partner: UNT Libraries Government Documents Department
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The Reaction of Zirconium with Uranium Dioxide

Description: An investigation of the causes of observed explosive reaction of zirconium-coated uranium dioxide on dissolution in nitric acid was conducted. It was concluded that such a reaction is to be expected. Possible but unconfirmed methods of alleviating the problem are suggested.
Date: June 11, 1957
Creator: Robinson, M. T.
Partner: UNT Libraries Government Documents Department
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HRP In-Pile Corrosion Test Loops -- Operation of In-Pile Loop L-2-10

Description: Loop L-2-10 was the eighth completed in-pile loop experiment and the first in the HB-2 beam hole at the LITR. The loop was inserted on July 2, 1956 and removed on September 3, 1956. The installation, operation, removal, and general performance of the HRP in-pile solution corrosion loop in the HB-2 beam hole at the LITR are described.
Date: June 13, 1957
Creator: Walter, F. J.
Partner: UNT Libraries Government Documents Department
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Fuel Exposures in Heterogeneous Thorium Breeder Reactors

Description: This technical report summarizes some preliminary calculations of fuel exposures attainable in heterogeneous reactors, fueled with a mixture of thorium and U233, moderated with D2O and operated with no net loss in fissionable fuel.
Date: June 13, 1957
Creator: Prince, B. E. & Jaye, S.
Partner: UNT Libraries Government Documents Department
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