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Thermal analysis of a SNAP-8 type reactor system during atmospheric reentry. Thermo-physics technical note No. 76

Description: A thermal analysis was carried out to determine the temperature distribution in a SNAP-8 type reactor system during atmopsheric reentry. Of particular interest are the temperature distributions in the reactor upper head, the upper grid plate, and the vessel wall. The time and altitude were determined at which the upper head falls away from the reactor core due to having a portion of its wall melted through. The time and altitude of the melting of the upper grid plate and vessel wall were also d… more
Date: July 12, 1966
Creator: Montgomery, L. D. & Mouradian, E. M.
Partner: UNT Libraries Government Documents Department
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Clad thickness variation N-Reactor fuel elements

Description: The current specifications for the cladding on {open_quotes}N{close_quotes} fuels were established early in the course of process development and were predicted on several basic considerations. Among these were: (a) a desire to provide an adequate safety factor in cladding thickness to insure against corrosion penetration and rupture from uranium swelling stresses; (b) an apprehension that the striations in the zircaloy cladding of the U/zircaloy interface and on the exterior surface might serv… more
Date: May 12, 1966
Creator: Smith, E. A.
Partner: UNT Libraries Government Documents Department
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Fast Flux Test Facility Fuel Handling System Group 40, fuel handling and radioactive maintenance objectives, requirements, and criteria

Description: This report discusses the objectives of the FFTF Fuel Handling and Radioactive Maintenance System Group which are: To remove and replace test components from the reactor core under a controlled environment to permit maximum acquisition and preservation of experimental data; to service and maintain the reactor core to enable maximum utilization of the irradiation capability of the facility; and to provide the radioactive maintenance capability consistent with the requirement for high plant facto… more
Date: October 12, 1966
Creator: Lenkersdorfer, H. D.
Partner: UNT Libraries Government Documents Department
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Sample calculation -- GVR values for determining tritium separations costs

Description: This paper shows the calculations for the Gas Volume Ratio, defined as the Total Gas Volume/Target Volume. Using 20 tons of LiAlO{sub 2} as the target, 5028 cubic feet of tritium, protium, and helium are produced. The target volume equals 312.5 cubic feet of aluminate, so that the GVR = 5028/312.5 = 16.1.
Date: December 12, 1966
Creator: Bown, R. W.
Partner: UNT Libraries Government Documents Department
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Theoretical density of lithium aluminate updated

Description: The ''handbook'' density for LiAlO/sub 2/ is 2.55 g/cc. Recent data show that it should be revised to 2.62 g/cc. In the future densities reported as percent of theoretical should be based on 2.62 g/cc as being 100 percent. Values quoted on this basis will be more realistic. In order to avoid confusion it will be necessary to state which number percent of theoretical density are based upon--that is, ''2.62 g/cc = 100 percent,'' or ''2.55 g/cc = 100 percent.'' For the convenience of those working… more
Date: January 12, 1966
Creator: Gurwell, W. E.
Partner: UNT Libraries Government Documents Department
open access

NRX/EST Test Prediction Report (U)

Description: The objectives of this test are to demonstrate the ability of a NERVA-type engine system to bootstrap from a tank pressure of 45 PSIA to full power, to study the stability of the control systems, to obtain high power mapping data and to demonstrate the stability of the core at high power. System response measurements will be conducted at both low and high power points to study the control systems. The operation of the engine at 4000{sup o}R chamber temperature will be mapped from design pressur… more
Date: January 12, 1966
Partner: UNT Libraries Government Documents Department
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Richland isotope production matrix

Description: Isotope production calculations have been prepared in the past to indicate present and potential reactor capability; however, the cases evaluated generally considered production of only one or possibly two isotopes. With the wide variety and potential demand for numerous isotopes, the question arises as to what the production capability would be if several isotopes were being produced at the same time. To study this problem in more detail and determine which of several alternates may be used in… more
Date: May 12, 1966
Creator: Kushler, L. E. & Shimer, R. D.
Partner: UNT Libraries Government Documents Department
open access

Status of special reactor-process tube loadings, September 1, 1966

Description: The attached pages show the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. For further description of column headings and the current discharge goal exposure plan refer to Document DUN-1048.
Date: September 12, 1966
Creator: Walton, R. P.
Partner: UNT Libraries Government Documents Department
open access

ORGDP Container Test and Development Program Fire Tests of UF6-Filled Cylinders

Description: Fire tests of bare, UF{sub 6}-filled shipping cylinders were conducted at the ORGDP Rifle Range during October 1965 as part of the AEC-ORO Container Test and Development Program presently under way at the ORGDP. The multi purpose effort was to determine if the cylinders would hydrostatically or explosively rupture; the time available for fire fighting before either incident occurred; and the degree of contamination as related to the type of UF{sub 6} release, wind velocity, and terrain. In addi… more
Date: January 12, 1966
Creator: Mallett, A. J.
Partner: UNT Libraries Government Documents Department
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Douglas United Nuclear, Inc., sponsored research and development programs, FY-1967

Description: Douglas United Nuclear, Inc., has allocated to the Pacific Northwest Laboratory $542,000 of 02 Research and Development funds and $455,000 of Process Technology funds for FY-1967. Of these, $392,000 of 02 Research and Development funds and $420,000 of Process Technology funds are the responsibility of the Research and Engineering Section. The balance in each case is the responsibility of the Production Fuels Section. Representatives of these Sections have met with Pacific Northwest Laboratory p… more
Date: July 12, 1966
Creator: Reid, R. W. & Stringer, J. T.
Partner: UNT Libraries Government Documents Department
open access

Status of Special Reactor Process Tube Loadings

Description: The pages of the report show the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. For further description of column headings and the current discharge goal exposure plan refer to Document DUN-1048.
Date: July 12, 1966
Creator: Walton, R. P.
Partner: UNT Libraries Government Documents Department
open access

Status of irradiations performed by testing for PNL as of December 10, 1965

Description: This document itemizes the irradiations performed by Irradiation testing for Pacific Northwest Laboratory. It lists the material undergoing radiation, awaiting disposition, and material shipped during the report period ending December 10, 1965. Materials irradiated were principally graphite but also included various steels and mixed fuel oxides.
Date: January 12, 1966
Creator: Ferguson, J.H.
Partner: UNT Libraries Government Documents Department
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