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Distribution coefficient data and preliminary estimates of movement of radionuclides, Tatum salt dome, Lamar County, Mississippi. Technical letter: Dribble 31

Description: Estimates are made relating radionuclide movement to ground water velocity as part of the safety program for a proposed experiment to detonate nuclear devices within the Tatum salt dome. The estimates are based on distribution coefficients obtained from laboratory studies. Core samples obtained from hydrologic test well HT-3, Tatum salt dome, Lamar County, Mississippi, were equilibrated with radionuclides in solutions simulating aquifer waters found in the area. The combinations of Cenozoic san… more
Date: April 10, 1963
Creator: Beetem, W. A. & Janzer, V. J.
Partner: UNT Libraries Government Documents Department
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Post-irradiation data on fuel elements from KER Loop 4

Description: Fourteen NAE1 fuel elements were discharged from KER Loop-4, after irradiation to an average exposure of 1250 MWD, at prototype N-Reactor coolant temperature and pressure. The elements were disassembled and measured in the KE fuel examination facility. This report includes all measurements, except the profilometer data.
Date: January 10, 1963
Creator: Bennett, E. C.
Partner: UNT Libraries Government Documents Department
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Fabrication of hot die size diffusion bonded fuel elements for Production Test IP-546-A

Description: Hot die sizing (HDS) is a process being considered at Hanford to replace or supplement the existing AlSi brazing process. Hot die sizing consists of passing a preheated core-component fuel assembly through a cold the to bond the aluminum jacket to the core while passing a die plug through the internal bore to form the internal bond. Fuel end bonding is accomplished in a following step by applying heat and pressure to the sized fuel element. This report summarizes the fabrication of fuel element… more
Date: October 10, 1963
Creator: Strand, C. A.
Partner: UNT Libraries Government Documents Department
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Old pile HCR operating temperatures

Description: A study was made to determine operating temperatures of old pile HCR sheaths. The calculations were performed with the aid of a FORTRAN coded program for the IBM 7090. The difficulty of determining the correct value for the contact coefficient between the HCR and the graphite channel at any point in the channel length resulted in performing the calculations in a parametric style. The independent system parameters were varied during the calculations. These parameters are diametral spacing betwee… more
Date: October 10, 1963
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Interim report I, production test IP-560-A, half-plant low dichromate: Low pH water treatment at C reactor

Description: Visual examination from 600 fuel elements., 300 discharged from the near side and 300 from the far side, showed the following results: (1) Primary ledge corrosion vas evident on 26 per cent of the fuel pieces, 21 per cent on the near side and 30 per cent on the far side. (2) Primary groove corrosion was evident on 3 per cent of the fuel pieces, 6 per cent on the near side and 1 per cent on the far side. (3) None of the fuel pieces exhibited severe localized corrosion. These results agree with p… more
Date: April 10, 1963
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
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Tube Wall Thickness Isotope Production Tubes

Description: Irradiation of process tubes containing appropriate parent materials has been proposed by Manufacturing as a method for obtaining new products from the Hanford Reactors. The process tubes would be removed at appropriate intervals and shipped to separations plants for recovery of the products. The tube residence in the reactor could be determined by the optimum irradiation period for isotope production rather than by the period required to corrode tubes of current design to the minimum permissib… more
Date: July 10, 1963
Creator: Young, J. R.
Partner: UNT Libraries Government Documents Department
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Design bases, Bauxite-sulfuric acid feed facilities 100-K area

Description: Criteria provided in this report delineate the objective, bases, and functional requirements that shall govern the preparation of detail design of the bauxite-sulfuric acid feed facilities to be installed in the 183-KE and KW Buildings. These facilities will produce the chemical coagulant used in the treatment of Columbia River water in the water plants and thus replace the existing liquid alum feed systems used for this purpose. The objective of this document is to define the operational and t… more
Date: June 10, 1963
Creator: Etheridge, E. L.
Partner: UNT Libraries Government Documents Department
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Calculations on close-coupled processing for Pu-238 recovery

Description: Irradiation of Np-237 in Hanford reactors and recovery of the Pu-238 product in a close-coupled separations plant is currently of interest. Such a concept has the potential of increasing in Pu-238 production rates. The results of initial calculations on the subject are presented herein to aid further study and evaluation. Much of the information is presented in terms of the aqueous target system proposed in earlier work (i.e., irradiation and processing of an aqueous neptunium solution). Howeve… more
Date: July 10, 1963
Creator: Coppinger, E. A.
Partner: UNT Libraries Government Documents Department
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INVESTIGATION OF VAPOR VOLUME FRACTION AND SLIP VELOCITY UNDER THE EURATOM PROGRAM. Quarterly Progress Report, July 1-September 30, 1963

Description: A literature survey was performed in order to provide an adequate basis for selecting models for comparison with the data. A computer program was written that allows calculation of void profiles based on an exponential model. A variable exponent is input data for the program, which also computes an integrated average void fraction. After the test section installation was completed, shakedown tests were performed to assure that all equipment was operating properly. All water and all air referenc… more
Date: October 10, 1963
Creator: Bezella, W. A.; Healy, M.; Kangas, G. J. & Neusen, K. F.
Partner: UNT Libraries Government Documents Department
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Laboratory reactor simulator

Description: No Description Available.
Date: December 10, 1963
Creator: Merchant, C.C. & Welsh, R.W.
Partner: UNT Libraries Government Documents Department
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IN-PILE RADIATION CORROSION EXPERIMENTS WITH ZIRCONIUM, TITANIUM, AND STEEL ALLOYS IN 0.17 m UO$sub 2$SO$sub 4$ SOLUTIONS AT 280 C

Description: In-pile loop experiments L-2-15 and L-4-16 were designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO/sub 2/SO/sub 4/ solutions. The solutions employed were 0.17 m UO/ sub 2/SO/sub 4/, 0.015 m CuSO/sub 4/, and 0.03 m H/sub 2/SO/sub 4/ in H/sub 2/O for experiment L-2-15, and 0.17 m UO/sub 2/SO/sub 4/, 0.015 m CuSO/sub 4/, and 0.025 m H/sub 2/SO/sub 4/ in H/sub 2/O for experiment L-4-16. The mainstream temperature in the experiments ranged … more
Date: July 10, 1963
Creator: Jenks, G.H. & Baker, J.E.
Partner: UNT Libraries Government Documents Department
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INVESTIGATION OF VAPOR VOLUME FRACTION AND SLIP VELOCITY UNDER THE EURATOM PROGRAM. Quarterly Progress Report, April 15, 1963-June 30, 1963

Description: Vapor volume fraction (void fraction) experiments using a gamma attenuation technique were planned. The experimental program required designing a test section and a steam generator. While the design of the test section was straightforward, the steam generator required considerably more attention because of the large flow and power requirements. Both designs were completed. All components of the gamma attenuation detection system were assembled and checked to be sure they were in proper operatin… more
Date: July 10, 1963
Partner: UNT Libraries Government Documents Department
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THE DEPTH-DOSE DISTRIBUTION PRODUCED IN A SPHERICAL WATER-FILLED PHANTOM BY THE INTERACTIONS OF A 160-Mev PROTON BEAM

Description: Measurements were made of the total energy deposited at various points within a 42-cm-dia spherical water-filled lucite phantom by the secondary particles resulting from 160-Mev proton reactions with various targets. Target materials were water, aluminum, carbon, copper, and bismuth. Detectors were small lucite-walled ionization chambers filled with 97% A--3% CO/sub 2/ or ethylene gas. Data were taken both with the lucite phantom on the beam axis and with the phantom offset approximately 54 deg… more
Date: July 10, 1963
Creator: Maienschein, F.C. & Blosser, T.V.
Partner: UNT Libraries Government Documents Department
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LCRE and SNAP 50-DR-1 programs. Engineering progress report, January 1, 1963--March 31, 1963

Description: Declassified 5 Sep 1973. Information is presented concerning LCRE specifications, primary coolant circuit, aaxiliary systems, fuel elements, instrumentation, materials development, and fabrication; and SNAP-50DR-1 specifications, fuel elements, pumps, steam generator, and materials development. (DCC)
Date: June 10, 1963
Partner: UNT Libraries Government Documents Department
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STEAM SEPARATION TECHNOLOGY UNDER THE EURATOM PROGRAM. Quarterly Progress Report, July 1, 1963-September 30, 1963

Description: Calibration of the liquid-level detector for steam-water facility is complete from 600 to 2000 psig. Permissible steam release rates for 24 and 36 inches above the interface are established for the test pressures. The correlalation equation which relates steam void fraction to basic system parameters is further refined to include ail the data from this program as well as from the low-pressure steam-water facility. By addition of another dimensionless term to the equation it is possible to exten… more
Date: October 10, 1963
Partner: UNT Libraries Government Documents Department
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STEAM SEPARATION TECHNOLOGY UNDER THE EURATOM PROGRAM. Quarterly Progress Report, April 1, 1963-June 30, 1963

Description: Installation of the test equipment and checkout of the steam-water test facility's controls for the first series of tests was completed with favorable results. Tests to determine the relation between steam void fraction and superficial steam velocity are complete through the pressure range of 600 to 2,000 psig. A correlation equation which relates steam void fraction to basic system parameters ia reported. The liquid level detector is in operation, and preliminary tests were performed. Detector… more
Date: July 10, 1963
Partner: UNT Libraries Government Documents Department
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ARMY REACTORS PROGRAM ANNUAL PROGRESS REPORT FOR PERIOD ENDING OCTOBER 31, 1962

Description: ; 8 7 < 8 < : : : 6 9 9 = < 9 < : 5 < > ;" icipation in the program continued to include review, inspection, and support in various areas of reactor technology. An advanced fuel irradiation test program was established that is to be conducted in the pressurized-water loop in the Oak Ridge Research Reactor. Review of the design of the MH-1A reactor was initiated. This reactor, a pressurized-water system fueled with low- enrichment bulk UO/sub 2/ clad with stainless steel, is being designed as a … more
Date: April 10, 1963
Partner: UNT Libraries Government Documents Department
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SHAPED BURNABLE POISON DEVELOPMENT PROGRAM UNDER THE EURATOM PROGRAM. Quarterly Progress Report, December 1, 1962-February 28, 1963

Description: Nuclear cross section data for gadolinium, Gd/sup 155/, and Gd/sup 157/ were compiled. Average absorption cross sections were computed assuming Maxwellian thermal spectra for moderator temperatures from 70 to 600 deg F. Poison demand curves were computed for a boiling water reactor with an H/sub 2/O- to-UO/sub 2/ ratio of 2.6, U/sup 235/ enrichments from 1.8 to 3.8 wt%, zirconium or stainless steel as clad, and fuel depletions of 10,000 to 25,000 Mwd/t. Based on the above poison demand curves, … more
Date: April 10, 1963
Partner: UNT Libraries Government Documents Department
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Summary Technical Report for the Period January 1, 1963 to March 31, 1963

Description: A semicontinuous ion exchange column was used for the pilot-scaie production of purified uranyl chloride solutions from scrap leach liquor. Continuous box mixer-settler tests demonstrated that an Aliquot-336--Solvesso 100 system will satisfactorily extract uranium from scrap leach liquor. An airless shot blaster is being used to clean slag from debries using uranium shot as the blasting medium. Plasma-spraying equipment was installed for coating graphite crucibles and molds with refractory mate… more
Date: May 10, 1963
Partner: UNT Libraries Government Documents Department
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STEAM SEPARATION TECHNOLOGY UNDER THE EURATOM PROGRAM. Quarterly Progress Report, January 1, 1963-March 31, 1963

Description: For purposes of analysis and experiment the centrifugal type downflow separator was divided into the inlet nozzle, separating zone, and outlet nozzle. The analysis and experiments have resulted in a new outlet design, a method of determining separating length, and a more effective inlet nozzle. The results have caused a reduction in pressure loss from 5 ft of water for the reference design to 1.5 ft of water for the new design at a flow rate of 1400 gpm. A reactor core riser and downcomer regio… more
Date: April 10, 1963
Partner: UNT Libraries Government Documents Department
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