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NACA Research Memorandums
4,120
NACA Technical Notes
2,223
Atomic Energy Commission Reports
1,874
United States Geological Survey Reports
1,253
Trace elements investigations report
749
Hanford Works Reports
710
University of California Radiation Laboratory Reports
484
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475
Oak Ridge National Laboratory Reports
473
NACA Technical Reports
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12,522 Matching Results
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Turbine Start-Up. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-179
The purpose of the test was to insure satisfactory operation of the turbine after overhaul of the turbine which was completed February 1, 1959. The operation of the turbine during this start-up was satisfactory.
Date:
December 14, 1959
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Corrosion of Type 202 Stainless Steel in High Temperature Water
The chromium-nickel-manganese alloys are a group of austenitic stainless steels which were developed during the Korean War to conserve nickel. These alloys are very similar to their corresponding 300 Series grades in mechanical, physical and corrosion properties. A portion of the nickel in the 300 Series grades has been replaced by approximately 2% manganese for each percent of nickel replaced. Two compositions, AISI 201 and AISI 202, are recognized as standard grades. Two other compositions, AISI 204 and AISI 204-L, have been produced in limited quantities to replace AISI 304 and AISI 304-L. Experience with the 200 Series steels indication they are every bit as good as the grades for which they were once alternates. In some shapes, such as rod and sheet, the cost per pound is considerably lower than the corresponding 300 Series grades.
Date:
December 11, 1959
Creator:
Larrick, A. P.
Object Type:
Report
System:
The UNT Digital Library
Design Studies on Cesium-137 as a Source for High Level Gamma Irradiators: Quarterly Progress Report Number 1, January - August 1959
Quarterly progress report describing work related to a study of radiation physics problems involved in the design of high-level cesium-137 gamma sources. It outlines work completed and ongoing goals for the project.
Date:
December 11, 1959
Creator:
Voyvodic, Louis & Stone, C. A.
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
Producibility of an Alloy of Columbium with One Percent Zirconium
Abstract. Proven mineral resources show that niobium is the most abundant of the refractory metals and extraction capacity is adequate to meet foreseeable requirements. Approximately four tons of Nb-1% Zr alloy were melted, forged, drawn, and rolled to produce various mill forms and relatively large die impression forgings. It was demonstrated that the Nb-1% Zr alloy is readily amenable to melting, primary working, and secondary working using standard equipment available in the specialty steel and nickel alloy industries. In general, the hot malleability of the alloy is significantly better than that of the more refractory nickel base high temperature alloys and is comparable to the stainless steels. Methods were successfully developed to protect the alloy against contamination during hot working. Cold fabricability proved to be outstanding. Reductions up to 90% were achieved during cold rolling of sheet with no intermediate stress relief or annealing treatment. Tube drawing reductions up to 50% were normal with no intermediate annealing. Over-all, the cold workability of this alloy was superior to that of the stainless steels. There was no problem of embrittlement over the full range of working temperatures which were used during the course of this work, namely from room temperature to 2350 …
Date:
December 9, 1959
Creator:
Raring, L M
Object Type:
Report
System:
The UNT Digital Library
Zirflex Dissolution of the Annular Cladding of Simulated Power Fuel Elements
The current interest in a tube-in-tube type Zircaloy-2 clad UO2 fuel element for use in the power reactors provided the incentive for a study of the dissolution of cladding from an annular space. The objectives of the study were to compare the estimated rate of dissolution in the annuli with rates on fully exposed metal. Because of an interest from the design standpoint, heat balance data from the study are reported.
Date:
December 9, 1959
Creator:
Smith, P. W.
Object Type:
Report
System:
The UNT Digital Library
Condensate System. Section II. Fifth Core I, Seed 1. Test Results DL-S-105
The purpose of the test was to fill the condensate storage tank and the Condensate System and obtain satisfactory preliminary operation. The components of the Condensate System performed adequately and satisfactorily with the exception of fill control valve (M9-VI). This valve (M9-VI) is not used in the current operation procedure.
Date:
December 8, 1959
Creator:
unknown
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
Study of Factors Influencing Ductility of Iron-Aluminum Alloys. Monthly Letter Report No. 8, 15 March 1959 to 15 March 1960
Studies are being made on the effects of variation of aluminum content, heat treatment, surface preparation, and other metallurgical factors on the room temperature ductility of Al-- Fe alloys. It is estimated that approximately 65 percent of the proposed research has been completed over the first eight and one-half months of the contract period.
Date:
December 8, 1959
Creator:
Perkins, Frank C. & Nachman, J. F. (Joseph F.)
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
The Fast Effect in a Beryllium Moderated Reactor
The effect of the (n, 2n) and (n, o<) reactions on the neutron economy of a beryllium moderated reactor is investigated.
Date:
December 7, 1959
Creator:
Novak, P. E.
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
Equilibrium Extraction Characteristics of Alkyl Amines and Nuclear Fuels Metals in Nitrate Systems. Progress Report No. V for the Period July 1 - September 30, 1959
Extraction of HNO3 by triaryl amine was studied by equilibrating equal volumes of aqueous and organic phases at 25C. At HNO3 concentrations of 2 to 10 N the acid in the organic phase in excess of that equivalent in the amine concentration was proportional to the concentration of HNO3 in the equilibrated aqueous phase. other workers report similar results with nitric acid and tri-n-octyl amine in benzene. Zirconium extractions carried out at 10g Zr/1 with 0.35 M TLA nitrate in toluene showed a fourth power dependence of EZR on HNO (aq) over the range 2 to 10N. Maximum distribution ratios calculated from samarium scouting experiments using amines in kerosene were about 5 x 10(-3) for Primene JMT, 10(-4) for TLA, 10(-5) for S-24, and less than zero for DTDA. Distribution rations in the extractions ranged from ERu = 0.12 for 0.35M TLA shaken with an initially new 2N HNO3 solution for 15 minutes. Data on Zr and Ru standardization in TLA solution for spectrophotometric analyses are included.
Date:
December 4, 1959
Creator:
Mason, Edward A. (Edward Allen), 1926-1994. & Vaughen, Victor C.
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
Autoclave Corrosion Behavior of U-Low Carbon and U-Low Zirconium Alloy Fuels
A preliminary evaluation of the autoclave corrosion behavior of a series of U-low C alloys and a series of U-low Zr alloys prepared by Fuels Fabrication Development Operation has been made. The corrosion testing was conducted by Coatings and Corrosion Operation by the experimental methods and procedure outlined in HW-61378.
Date:
December 1, 1959
Creator:
Goffard, J. W.
Object Type:
Report
System:
The UNT Digital Library
Biological Effects of Radiation, and Related Biochemical and Physical Studies : Semiannual Progress Report [for] Period May 1, 1959 - October 31, 1959
Progress reports from four divisions are included: (1) Division of Biophysics; (2) Division of Clinical Investigation; (3) Division of Nucleoprotein Chemistry; and (4) Radiochemistry Section.
Date:
December 1, 1959
Creator:
Denues, Arthur Russell Taylor, 1914-
Object Type:
Report
System:
The UNT Digital Library
Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements
Report issued by the Argonne National Laboratory over studies conducted on the Argonne Low Power Reactor. As stated in the abstract, "this report describes the manufacture of 1150 fuel core blanks, of which 816 were used in the fabrication of fuel elements. Development, casting, hot and cold rolling, cleaning, and punching of core blanks are discussed, as are nondestructive testing and evaluation of the manufacturing processes" (p. 7). This report includes tables, illustrations, and photographs.
Date:
December 1959
Creator:
Salley, R. L. & Burt, W. R., Jr.
Object Type:
Report
System:
The UNT Digital Library
Comments on Equipment for a PRTR Water Quality Control Laboratory
This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating personnel may be used to provide analytical coverage on those routine analyses that are needed on around-the-clock basis with a savings of both time and money.
Date:
December 1, 1959
Creator:
Anderson, H. J. & Peray, R. E.
Object Type:
Report
System:
The UNT Digital Library
Experimental Organic Cooled Reactor : Conceptual Design
Report presenting the design, research programs, and design objectives for an Organic-Cooled Reactor.
Date:
December 1, 1959
Creator:
Huffman, John R.; Nyer, W. E. & Rainwater, J. H.
Object Type:
Report
System:
The UNT Digital Library
Hazards Evaluation Report Associated with the Operation of EBWR at 100 MW
Hazard report on the Experimental Boiling Water Reactor that covers the basic modifications to the plant as designed to increase the present operating design rating of 20 Mw(t) to a new rating of 100 Mw(t). Changes and additions to the plant, core, reactor vessel, and other major components are shown. An analysis of the effects of the changes on the performance and safety of the reactor is presented.
Date:
December 1959
Creator:
Wimunc, E. A. & Harrer, J. M.
Object Type:
Report
System:
The UNT Digital Library
High-Dielectric-Constant Materials as Capacitor Dielectrics : a Study in Dielectric Spectroscopy
A fundamental study is presented comparing the electric properties for materials of "normal" dielectric constant (Al/sub 2/O/sub 3/ and MgTiO/sub 3/) with those of high dielectric constant (TiO/sub 2/, CaTiCO/sub 3/, SrTiO/sub 3/, STABa/sub 0.65Sr/sub 0.35/! STATiO/sub 3/, and BaTiO/sub 3/). Single crystals and ceramics, as far as available, were investigated from d-c to the microwave range as function of time, temperature, field strength, and prehistory. Three types of relaxation spectra were identified, one caused by dipolar groups in unequal double wells, the other two by charge carriers stopped in the volume of the material or in front of the electrodes, respectively, O-H groups in rutile, identified by infrared absorption, seem to cause a dipolar spectrum by thermal excitation leading to hydrogen-bond formation. The shielding of dipoles by countercharges (dipole halos) is probably responsible for the unequal potential wells and likely to be a phenomenon of general importance. Electrons can be injected into rutile and other titanates by field emission. Parallel to the optic axis of rutile, the conduction currents reach especially high values because of an unhampered Ti/sup 3+/ yields Ti/sup 4+/ exchange, and thermal breakdown by field-emission currents occurs. Pure titania materials at high temperatures become very lossy …
Date:
December 1959
Creator:
Von Hippel, Arthur R. (Arthur Robert), 1898-2003 & Westphal, W. B.
Object Type:
Report
System:
The UNT Digital Library
Initial Testing and Operation of the Argonne Low Power Reactor (ALPR)
From Introduction: "In this report data are presented on the various phases of the program, together with test results and recommendations for future plant improvements. The ALPR prototype has proven to be a stable and reliable nuclear power plant."
Date:
December 1959
Creator:
Hamer, Eberhard E.
Object Type:
Report
System:
The UNT Digital Library
Liquid Metal Fuel Reactor Experiment, Cavitation by Bismuth
From abstract: "Croloy 2 - 1/4 was tested to determine the causes and effects of cavitation in dynamic liquid bismuth solutions."
Date:
December 1959
Creator:
Hovanec, F. L.
Object Type:
Report
System:
The UNT Digital Library