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Office of Scientific & Technical Information Technical Reports
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491
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88
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2,279 Matching Results
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Chemical Development Section C Monthly Progress Report August 1959
Uranium extractions from carbonate solutions were effective and phase separation rates were rapid using a new commercial quaternary extractant, Alamine 336. Extraction coefficients were approximately proportional to the quaternary concentration. Addition of -0.5 mole tridecanol/mole quaternary to the solvent gave optimum extraction efficiency and phase separation rates.
Date:
September 8, 1959
Creator:
Brown, K. B.; Allen, K. A.; Coleman, C. F.; Crouse, D. J. & Ryon, A. D.
Object Type:
Report
System:
The UNT Digital Library
Secondary-Side Water Treatment for Corrosion Control in Aluminum Heat Exchangers: Practices and Results at the Oak Ride Research Reactor
Standard water treatment practices have proven adequate for scale and corrosion control on the secondary side of the ORR pool-cooling heat exchanger. Corrosion rates measured on specimens exposed to secondary water showed maximum corrosion rates of approximately 1 mpy during the first exposure period and these rates decreased during subsequent exposure.
Date:
August 12, 1959
Creator:
P. D. Neumann
Object Type:
Report
System:
The UNT Digital Library
Periodic Radiation Survey. Section I. EFPH-5465.2. Second Performance. Core I, Seed 1. Test Results DL-S-231, T-612394
The purpose of the test was to determine the radiation levels in a Reactor Plant Boiler Compartment with the respective loop shut down and the remainder of the plant operating at power. The highest radiation levels recorded in the IC Boiler Compartment were located in the vicinity of the reactor coolant loop pipe penetrations of the Compartment. Except for the above mentioned areas, personnel could continuously occupy the IC Boiler Compartment without exceeding the maximum dose rate of 300 mr per week. The areas in the vicinity of the reactor coolant pipe penetrations, however, could be occupied only 1 to 2 hours per person per week because of the high radiation levers (200-250 mr/hr) present at these locations.
Date:
December 16, 1959
Creator:
McTish, James M.
Object Type:
Report
System:
The UNT Digital Library
1A Reactor Inlet Hydraulic Valve Position Detector Temperature. Section I. Core I, Seed 1. Test Results DL-S-258-S, RNI-3
The purpose of the test was to determine the internal temperature of the valve position detector for the 1A reactor inlet hydraulic valve with the plant at normal pressure and temperature and at power. The normal operating temperatures for the valve position detector on the 1A reactor inlet hydraulic valve range from a minimum of 287 F to a maximum of 294.7 F.
Date:
November 20, 1959
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Leveling of Extraction Tool Crane Rails. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-246, FY-59-323
The purpose of the test was to check the extraction crane rails in the area of the reactor pit for level and parallelism. The west extraction crane rail exceeded the allowed tolerance of 1/32 inch at only one location. The elevation of the north bumper was out of tolerance by 1/64 inch. The east extraction crane rail was consistently lower than the west rail by as much as 8/64 inch. The east rail was parallel with the west rail within allowable tolerances over the length tested except at one location where the transit was located, approximately 41 feet from the north bumper.
Date:
November 30, 1959
Creator:
Pazuchanics, Nicholas
Object Type:
Report
System:
The UNT Digital Library
Determination of Possible Failed Blanket Elements Using the FEDAL System. Section I. First Performance. Core I, Seed 1. Test Results DL-S-2810S, RNI-24
The purpose of the test was to determine if failed blanket elements exist in other regions of the core beside F-2. FEDAL sampling ports that have indicted the greatest deviation as determined in a statistical analysis performed on a number of traverses in the FEDAL system will be tested. Data obtained from the start up runs of the FEDAL sample port Nos. 11, 31, 36 and 37 of Monitor 2 and port Nos. 14, 46, 11, 49 and 7 of Monitor 1 gave no indications of a blanket element failure. At each power increase, the radiation increase was normal with no signs of bursts or peaks of radiation which would indication the failure of a blanket fuel element.
Date:
November 23, 1959
Creator:
Pazuchanics, Nicholas & Kearns, Walter
Object Type:
Report
System:
The UNT Digital Library
Periodic Radiation Survey. Section III. First Performance. Core I, Seed 1. Test Results DL-S-231, T-612394
The purpose of the test was to determine the radiation levels inside the concrete enclosures but outside the reactor plant containers after shutdown following plant power operation. Radiation levels at the survey points in the 1-AC and 10BD Boiler Chambers Enclosures and in the Reactor Container Enclosure indicated that no significant radiation hazards were present approximately 25 minutes after all rods had been inserted. The radiation levels approximately 4 minutes after shutdown at the survey points in the Auxiliary Chamber Enclosure indicated that several points were above background, the highest test level being obtained in contact with the East Auxiliary Chamber container drain pipe.
Date:
November 30, 1959
Creator:
Shramko, John, Jr.
Object Type:
Report
System:
The UNT Digital Library
Examination of Components for Crud and Corrosion. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-155, T-612080
The purpose of the test was to observe the extent and location of corrosion, crud deposits and defects in components of the primary fluid system and its auxiliaries. This observation will allow an estimate to be made of the future behavior of the affected parts. The test also provides for obtaining corrosion products and crud samples for analysis as necessary for planning remedial actions. This test was limited to the 1D Main Coolant Pump which failed November 3, 1958. The pump failed after 2234 hours of operation on "fast" speed and 887 hours at "slow" speed. An inspection for corrosion was not conducted but smear samples were taken and a radiochemical analysis made. This analysis showed the following isotopes were present in the smear sample: Co38, Co60, Fe59, Mn54, Hf191 and Zr95. The upper and lower radial pump bearings and journals were severely scored and galled while the thrust bearing and runner appear to be in good condition.
Date:
December 7, 1959
Creator:
Muldoon, James B.
Object Type:
Report
System:
The UNT Digital Library
Charging and Discharge of Demineralizer Resins. Section IV. First Performance. Core I, Seed 1. Test Results DL-S-180, T-612085
The purpose of the test was to determine if the 1A Canal Water System Demineralizers can be satisfactorily charged with resin. The 1A Canal Water System Demineralizer was satisfactorily charged with resin and conductivity of the demineralizer effluent was less than 0.1 microbes as specified in the Test Procedure.
Date:
December 3, 1959
Creator:
Eckenrode, G. E.
Object Type:
Report
System:
The UNT Digital Library
The Determination of Decontamination Factors for Radioisotopes Through Lithium Hydroxide Resin. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-277-S, RNI-22
The purpose of the test was to obtain data on the decontamination factors for Cesium-136, Cesium-137, Strontium-92, one hour gross iodine and Iodine-131. This data will be used to determinate efficiency of lithium hydroxide resin for removing radioactive cations and anions. The denomination factors for a particular demineralizer using lithium hydroxide resign were found to vary for different radioisotopes. This variation was from 2.3 for Cesium136 to 77,000 for gross iodine.
Date:
December 3, 1959
Creator:
Strauos, Roger O.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Instrumentation Operation During Plant Operation. Section I. First Performance. Core I, Seed 1. Test Results DL-S-309, RNI-41
The purpose of the test was to evaluate the operation of the Nuclear Instrumentation Power Range Amplifier during start up. While the station was operating at a gross load of 16.5 megawatts, a variation of 0, 8.5, 2.7 and 4.4 existed between the compensated ion chamber currents (CIC) and the test currents for channels A, B, C and D respectively. The off site modifications to channel C power range amplifier did not cause the ion chamber current and test current to be the same at 16.5 megawatts gross power. The modifications to channel C were made to correct for this deficiency.
Date:
December 8, 1959
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Main Coolant Pump Performance Test. Section I. First Performance. Core I, Seed 1. Test Results DL-S-290, T-641326
The purpose of the test was to obtain performance data for the main coolant pumps on fast and slow speed at various coolant temperatures. The 1A, 1B and 1C pump performances on both fast and slow speed were approximately as shown in the manufacture's predicted performance curve. The 1D pump performance was below the manufacturer's predicted flow efficiency, line current and hydraulic horsepower on both fast and slow speeds.
Date:
December 7, 1959
Creator:
Edwards, Gerald E.
Object Type:
Report
System:
The UNT Digital Library
Control Rod Positions for Criticality. Section I. 5032-EFPN. Eigth Performance. Core I, Seed 1. Test Results DL-S-149, T-550130
The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at ambient temperatures. The critical rod bank position and bank worths for four different control rod bank rod configuration were determined after 5032 EFPH's of operation. The value were corrected to a reactor coolant temperature of 145 F and a pressure of 400 psig. The bank worths were corrected to 145 F so that the results of the performance could be compared with the results of previous performances.
Date:
December 9, 1959
Creator:
McTish, James M.
Object Type:
Report
System:
The UNT Digital Library
Core I Control Rod Drive Mechanisms Periodic Tests. Section I. Ninth Performance. Test Results DL-S-148-I, T-550011
The purpose of the test was to determine the operating conditions of the rod drive mechanisms so that operating personnel may be informed concerning malfunctioning mechanisms. The results the this test favorably agree with previous results. The operating characteristics of the rod drive mechanisms checked in this test have not changed appreciably.
Date:
November 18, 1959
Creator:
Pazuchanics, Nicholas
Object Type:
Report
System:
The UNT Digital Library
Present Status of Semiconductor Particle Counters
This review lists some of the salient features of semiconductor particle counters and cannot claim to contain an exhaustive listing of all the work in the field. Performance results on the surface-barrier counters as developed at California Institute of Technology are included as typical for this type of counter, though comparable results have been obtained elsewhere.
Date:
November 23, 1959
Creator:
Barnes, C. A.
Object Type:
Report
System:
The UNT Digital Library
Fission Gas Generation and Consequent High Temperature Irradiation Effects on Natural Uranium, Including Creep Properties : a Literature Search
Sixty-two references, some annotated, were taken from foreign literature to determine the status of work done in this area of metallurgy during 1958 and 1959. The references are grouped into two categories: references pertinent to the subject and general metallurgical references on metallic fuels.
Date:
December 15, 1959
Creator:
Scott, Myra
Object Type:
Report
System:
The UNT Digital Library
Organic Coolants and Moderators for Nuclear Reactors : a Literature Search
A literature search was made of Nuclear Science Abstracts , Vols . 12 and 13 , for information on the following organic coolants and moderators for nuclear reactors : biphenyl , diphenyl methane , Dowtherm A , a phenyl naphthalene, and terphenyl. The properties covered include: thermal and irradiation stability, methods for restoring desired properties to used material, heat transfer data, operating information, hazards and toxicity. 111 references to documents, journal, and books are listed.
Date:
December 1959
Creator:
Kauer, E. U.
Object Type:
Report
System:
The UNT Digital Library
Final Technical Report on Physics Research
Results are summarized on theoretical considerations of the excited states of the Ca isotopes, experimental studies of the level structure of Ca42 and Ca44, studies of the production of circularly polarized bremsstrahlung by beta rays, the Moller scattering spectrometer, and the Moller scattering coincidence experiment.
Date:
November 30, 1959
Creator:
McCullen, J. D.; Kraushaar, J. J.; Woolum, J. C.; Sandifer, C. W.; Kliwer, J. K.; Baker, D. et al.
Object Type:
Report
System:
The UNT Digital Library
Absorption of Radionuclides Applied to Above Ground Plant Parts : Terminal Report
The attached list of publications is submitted as a year to year and final report of progress on work accomplished under Contract AT(11-1)-159 from 1950 to 1959. Work was initiated on this project in the spring of 1950 and is still in progress as of the date of this report.
Date:
1959
Creator:
Wittwer, S. H. (Sylvan Harold), 1917-2012; Turkey, H. G. & Bukovac, M. J.
Object Type:
Report
System:
The UNT Digital Library
Studies of Reactor Containment : Monthly Technical Progress Report No. 29
The report covers work performed during the period September 1, 1959 through September 30, 1959. The general objectives of the program of "Studies of Reactor Containment" are to accomplish theoretical and experimental investigations of the loads to which external containment structures for nuclear reactors are subjected in the vent of a violent incident at the reactor core, the evaluation of methods of reducing that loading, and the study of the response of and design criteria for external containment structures as a result of such loading. Progress of technical effort during the report period is summarized for each of the eight tasks of the program.
Date:
October 23, 1959
Creator:
Zaker, T. A. (Thomas Allen)
Object Type:
Report
System:
The UNT Digital Library
Shippingport Atomic Power Station : Monthly Operating Report, November 1959
The Monthly Operating Report is divided into seven major sections: Summary of Report, Station Activity Schedule, Operations, maintenance, Refueling, Test Program and Training Program.
Date:
1959
Creator:
Oldham, G. M.
Object Type:
Report
System:
The UNT Digital Library
Determination of Flux Levels in Neutron Detector Wells. Section II. First Performance. Core I, Seed 1. Test Results DL-S-242, T-641311
The purpose of the test was to determine the neutron flux level in a BF3 counter well during the second performance of DL-S-225. The measured activity of the irradiation brass bolt was due entirely to the radioactive decay of Zn65. The thermal neutron flux in the BF3 counter well during the second 1000 hour run was calculated to be 2.5 x 10(9) neutrons/cm2 sec.
Date:
October 30, 1959
Creator:
George, John R. & Cappola, M., Jr.
Object Type:
Report
System:
The UNT Digital Library
Thorium Bismuthide : Ultrasonic Control of Crystal Size
Thorium bismuthide when crystallized from a solution i bismuth results in large platelets which may be as large a 1 centimeter in diameter. A slurry of these platelets is difficult to pump through pipe lines and filters. The particle size can be reduced by (1) very rapid cooing (approximately 1000 degree C per second) or (2) ultrasonic treatment. The latter, much easier to attain in large scale, gives equiaxed particles of thorium bismuthide.
Date:
March 16, 1959
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Absorption of Organic Acids on Thoria
The adsorption of acetic and oleic acids on the surface of thoria was studied by means of infrared spectroscopy. An infrared analysis of the adsorbates before and after adsorption using differential double bean methods indicated that the adsorption of organic acids on thoria surfaces occurs by an esterification reaction between the organic acid and the hydroxylated thoria surface. Ammonia vapor will not adsorb on thoria, indicated the basic character of the hydroxylated surface.
Date:
December 31, 1959
Creator:
Bradford, Harold R. & Wadsworth, Milton E.
Object Type:
Report
System:
The UNT Digital Library