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Evaluation of macroreticular anion exchange resin - RTA-893-R

Description: The macroreticular anion exchange resin, Amberlite IRA-900-OH, and an experimental resin from Ionac Chemical Company were irradiated by a /sup 60/Co source to doses of 5 x 10/sup 7/ rad and 10/sup 8/ rad. These doses approximate or exceed the dose encountered by the deionizer resins in 100-Area service. The loss in exchange capacity and the volume changes of Amberlite IRA-900 on irradiation were similar to those found previously for Amberlite IRA-400. The Ionac experimental resin, which had a c… more
Date: June 7, 1965
Creator: Baumann, E. W.
Partner: UNT Libraries Government Documents Department
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Bibliography on Pion-Pion Interaction

Description: A bibliography on pion-pion interactions is presented. The 241 references are those available through November 7, 1961. A chronological listing is given together with excerpts or comments. In another part the references are grouped according to subject. An author index is included. (M.C.G.)
Date: November 7, 1961
Creator: Stevenson, M. L.
Partner: UNT Libraries Government Documents Department
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PION SCATTERING FROM A POLARIZED TARGET

Description: This report describes the use of a target containing polarized protons in a particle-scattering experiment. Positive pions of 246-MeV kinetic energy were scattered from the polarized protons. The parameter P that was measured is equivalent to that determined by analyzing the recoil-proton polarization in scattering from an unpolarized target. It has been measured to a higher accuracy than heretofore achieved in pion-proton scattering, at an energy and at angles inconvenient for double-scatterin… more
Date: August 7, 1963
Creator: Chamberlain, Owen; Jeffries, Carson D.; Schultz, Claude H.; Shapiro, Gilbert & Van Rossum, Ludwig.
Partner: UNT Libraries Government Documents Department
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The Boron-Carbon System: Final Technical Report, May 1, 1960 - April 30, 1961

Description: Abstract: The boron-carbon equilibrium diagram has been determined by X-ray, metallographic, and thermal analysis of sintered and arc-cast alloys. A single carbide having a range of solubility from approximately 9 to 20 a/o carbon and melting congruently exists in the system. The terminal solubility of carbon in boron is 0.1-0.2a/o. The freezing reaction at the composition and melting temperature of elemental boron; there is a eutectic reaction at 29a/o carbon and 2375 degrees Celcius. No allot… more
Date: June 7, 1961
Creator: Elliott, Rodney P.
Partner: UNT Libraries Government Documents Department
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An Experimental Gamma Irradiator for Hospital Sterilization

Description: From foreword: This report presents the preliminary design of a gamma irradiator intended for use as an experimental hospital sterilizer.
Date: March 7, 1960
Creator: Frankfort, J. Harry; Haram, S. & Wallach, S.
Partner: UNT Libraries Government Documents Department
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Accidental nuclear excursion recuplex operation 234-5 facility: Final medical report

Description: The April 7, 1962 criticality accident involving human exposures was the first to have occurred in any production facility at Hanford. The accidental nuclear excursion did not result in any mechanical damage or spread of contamination. Three employees received over-exposure to gamma and neutron radiation. None were fatally exposed and in each case the over-exposure was recognized promptly. Following an initial period of medical observation and testing, the men were released to work. They contin… more
Date: April 7, 1962
Partner: UNT Libraries Government Documents Department
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Thermo-physics technical note No. 37: SNAP- 10A, Stainless Steel-316 vessel wall ablation. Final report

Description: The altitudes and times of ablation have been determined for the SNAP-10A, SS-316 vessel wall reentering under various conditions. The results are confined to one typical location on the reactor and to one typical reentry trajectory. The location is the side wall of the vessel and the trajectory is the one used in NAA-SR-8303.
Date: December 7, 1964
Creator: Montgomery, L.D.
Partner: UNT Libraries Government Documents Department
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Thermo-physics technical note No. 56: a parameter study of properties and mechanisms affecting the reentry ablation of SNAP fuel particles

Description: The results are presented of a parameter survey of the properties and mechanisms affecting the reentry ablation of SNAP fuel particles. The following properties and mechanisms were studied: aerodynamic heating, oxidation, oxide vaporization, metal vaporization, particle emissivity, specific heat, density, velocity, and initial size. These studies were made for particle release altitudes ranging from 170,000 to 228,000 feet.
Date: December 7, 1965
Creator: Sayles, C.W.
Partner: UNT Libraries Government Documents Department
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Radioisotope concentrations in the PRTR primary coolant and helium system during operation with a failed fuel element(s)

Description: Fission product measurements in the PRTR primary D{sub 2}O and helium systems during the startup tests in May 1961, showed the presence of a defective fuel elements(s). Reactor operation was discontinued during the latter part of May and during June for reactor maintenance and fuel element inspection. On resumption of operation on July 1, a sampling and analytical program was initiated to study the radioisotope concentrations resulting from this defective element(s) which were present in the pr… more
Date: September 7, 1961
Creator: Perkins, R. W. & Thomas, C. W.
Partner: UNT Libraries Government Documents Department
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Planned normalization of plutonium yield predictions to the twelve two-ton test batch measurements

Description: This report is a comparison of findings from the twelve two-ton test batches irradiated in the KE and H reactors with respect to reactor plutonium yield predictions. Included are plans for the application of these findings to improve the accuracy of plutonium yield equations used for Hanford product accountability.
Date: June 7, 1961
Creator: Hoba, D. W. & Vaughn, A. D.
Partner: UNT Libraries Government Documents Department
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AlSi slopovers: studies, method of elimination and results

Description: During fuel element assembly, a dip-brazing process., the aluminum can which is ultimately a jacket for a uranium core is protected from the molten AlSi solution by a steel sleeve. Once the can is inserted into the sleeve and thermal expansion is complete, upset metal rings prevent molten AlSi from flowing between the can and sleeve, a situation that warrants rejection. Passage of molten solution beyond upset metal to a point on the can wall not removed during the subsequent facing operation is… more
Date: December 7, 1963
Creator: Schaffer, J. D.
Partner: UNT Libraries Government Documents Department
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Minimizing consequences of an attack threat

Description: Assistance was requested in reviewing and comparing certain measures that could be effected immediately with little capital cost to render the plant less vulnerable to self-destruction in case of a war situation that made it impossible to man the water plants. Several courses of action have been considered with the assumptions detailed.
Date: December 7, 1962
Creator: Pirode, C. A.
Partner: UNT Libraries Government Documents Department
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Report to the working committee from the General Electric Company, HAPO

Description: Information is presented on current reactor fuel development (uranium core production data, fuel performance, AlSi process development, and alternate process development) and NPR fuel development (fuel production status, KER loop testing, and process development).
Date: January 7, 1963
Creator: Stringer, J. T. & Minor, J. E.
Partner: UNT Libraries Government Documents Department
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KER loop rupture summary

Description: This report is a compilation of available data on ruptures that have occurred since KER start-up. Some of the data presented in this report are inconclusive, but are reported to insure a complete summary of all potential and confirmed ruptures.
Date: January 7, 1960
Creator: Buckner, C. L.
Partner: UNT Libraries Government Documents Department
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