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Modified Purification System Performance Test. Core 1, Seed 2. Test Results T-641124-A. Section 2

Description: The effectiveness of purification in controlling plant radioactivation rates was determined through comparison of the actual effects produced from plant operation with and without purification. With the purification system in service, there was no appreciable difficulty in maintaining the reactor coolant within reference water specifications. In addition, there was no discernible increase of crud deposition in the coolant system as determined by direct radiation measurements of the purification hairpin loop. However, without demineralization as a controlling agent, the gross non-volatile gamma activity levels of the reactor coolant increased and the specific activities of longlived fission products were at higher levels. Although the general levels of water- borne activities increased during the test period, the associated plant systems did not exceed their limits. (auth)
Date: July 21, 1961
Partner: UNT Libraries Government Documents Department
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EQUIPOISE-3: A TWO DIMENSIONAL, TWO-GROUP, NEUTRON DIFFUSION CODE FOR THE IBM-7090 COMPUTER

Description: EQUIPOISE-3 is an IBM-7090 FORTRAN programmed code for the solution of two-group, two-dimensional, neutron diffusion equations. A maximum of 2l00 mesh points may be used, and the code will solve problems in either rectangular or cylindrical geometry. Logarithmic derivative boundary conditions are allowed, and removal of neutrons from both groups is permitted. Adjoint fluxes with the associated fluxadjoint flux regional integrals may be calculated automatically if desired. A constant buckling, group-dependent buckling, or region-dependent buckling may be specified for rectangular geometry. This program is intended to fill the need for a rapid two-dimensional calculation suitable for survey calculations. During the iterative part of the computations, all operations are carried out in the core memory. The magnetic tape memory is used only for input, output, and program storage. The running time for a 1000-point problem requiring 100 iterations would be about 3 min.(auth)
Date: February 21, 1962
Creator: Fowler, T.B. & Tobias, M.L.
Partner: UNT Libraries Government Documents Department
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CHEMICAL TECHNOLOGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961

Description: Activities in research programs are summarized in the areas of power reactor fuel processing, fluoride volatility processing, molten salt reactor fuel processing, homogeneous reactor fuel processing, waste treatment and disposal pilot plant decontamination, GCR coolant purification studies, equipment decontamination, HRP thoria blanket development, fuel cycle development, transuranium element studies, production of U/sup 232/, uranium processing, fission product recovery, thorium recovery from granite, solvent extraction technology, mechanisms of separation processes, radiation effects on catalysts, ion exchange technology, chemical engineering research, chemical applications of nuclear explosions, reactor evaluation studies, and assistance programs. (J.R.D.)
Date: September 21, 1961
Partner: UNT Libraries Government Documents Department
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[News Script: Murder]

Description: Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date: September 21, 1968
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
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Selected Statistics relating to Firearms

Description: This report describes the statistics concerning due to firearms. For these statistics, the United States has two sources: The U.S public health service, bureau of vital statistics, and the federal bureau of investigation.
Date: June 21, 1968
Creator: Olguin, Mary
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF RING-JOINT FLANGES FOR USE IN THE HRE-2

Description: Ring-joint flanges were studied in thermal-cycle tests as part of the development work associated with Homogeneous Reactor Experiment No. 2 (HRE-2). The purpose of this study was to provide criteria for design, installation, and operation of joints that would remain leaktight under reactor operating temperatures and pressures. Joints ranging from 1/2 in., l500 lb to 4 in., 2500 lb and with various initial bolt loadings were cycled between room temperature and 636 deg F. It was demonstrated that when joints were made up to HRE-2 standards and specifications, leak rates of less than 0.25 x 10/sup -3/ g of water per day per inch of gasket pitch diameter could be routinely- attained. Undamaged gaskets could be reinstalled or new gaskets used with equal probability of achieving acceptable leak rates. The system installed in HRE-2 was provided with a high-pressure buffer system to ensure that the small amount of leakage to the cell would be nonradioactive. (auth)
Date: December 21, 1961
Creator: Robinson, J. N.; Lundin, M. I. & Spiewak, I.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section C Progress Report for October-December 1961

Description: Recovery of Th (and U) from Granitic Rock. Recovery of Th by acid leaching ten addltlonal granite samples (36 to 82 ppm Th) from the Conway formation in N. H. ranged from about 50 to 85%, and averaged about 70%, Study of the effect of grind size on the recovery of Th from Conway and Plkes Peak granites showed no significant differences in the range minus 20 to minus 200 mesh. The Th concentration in a sized Conway granite sample was found to be much greater in the fine than in the coarse fractions, whereas Pikes Peak granite showed only slight Th enrichment in the finer fractions. U recoveries in acid leaching of four different granite samples were not improved by adding an oxidant. Collection and Analysis of Granite Samples. A field survey of the Conway granite formations in N. H. was made. Preliminary analysis of the data indicates that the accessible surface of the Conway granite averages at least 40 ppm Th. Collection and Analysis of Lateritic Soils. The Th concentration ranged 5 to 16 ppm in twenty-two samples of sub-lateritic soil from Miss., Ala., Ga., and Va. Final Cycle Pu Recovery by Amine Extraction. In continued batch countercurrent testing with simulated Purex 1BP solution of the proposed chemical flowsheet for final cycle Pu recovery by amine extraction, the extraction profile with the amine (TLA) concentration decreased from 0.3 to 0.15 M again confirmed the predicted extraction isotherm. The product solution contained 23 g Pu/liter (nominal x20 concentration factor), and the stripped organic and the raffinate contained, resp., 0.001 and <0.002 g/liter. Extraction and Separation of Zr and Hf. Results are summarized for tests on the extraction and separation of Zr and Hf with amines and organophosphorus esters and acids. All three extractant classes showed some promise but the …
Date: February 21, 1962
Creator: Brown, K.B.
Partner: UNT Libraries Government Documents Department
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Effects of the Maximum Credible Accident Relevant to the Design of the Containment Shell, Experimental Low-Temperature Process Heat Reactor Project

Description: The effects of the maximum credible accident relative to the design of the containment shell are discussed. The maximum credible accident is defined. The thermal and hydraulic effects of the maximum credible accident on the reactor system were analyzed. The extent to which fuelrod cladding will melt was estimated. The amount of energy released from the reactor system by the escaping steam and water and by a possible chemical reaction was calculated along with the corresponding pressure rise inside the containment shell. The kinds, amounts, and total radioactivity of fission products released to the atmosphere of the containment shell after the core melts were predicted. (M.C.G.)
Date: March 21, 1960
Partner: UNT Libraries Government Documents Department
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