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Evaluation of the ``machined parts`` cask for off-site shipments of irradiated lithium

Description: The ``machined parts`` casks are shipped to Hanford by Savannah River for loading with irradiated lithium alloy slugs and returned for processing. The casks have been in service for about 10 years and have shielding material more than what is required by regulations for radiation attenuation. Evaluation shows that rupture of the shell is probable for edge or corner drop, with considerable displacement of shielding. The cask would fail in a 2-hour fire of 2000 F with loss of shielding and probab… more
Date: July 12, 1963
Creator: Peck, G. E.
Partner: UNT Libraries Government Documents Department
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Evaluation of the B-cask in accordance with proposed regulations of the AEC and ICC for off-site shipments of irradiated bismuth

Description: The growing concern of government agencies for safe shipment of radioactive materials, both in this country and in Europe, has resulted in a number of proposed regulations governing every phase of shipment including the design of the cask or container, There have been requests during the last year for increased shipments of irradiated bismuth from Hanford. This radioactive material has been shipped in the B-cask to the off-site processing plant for several years. These two factors, proposed reg… more
Date: July 12, 1963
Creator: Peck, G. E.
Partner: UNT Libraries Government Documents Department
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Status of special reactor-process tube loadings, July 1, 1967

Description: The attached pages show that 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, 1967
Creator: Walton, R. P.
Partner: UNT Libraries Government Documents Department
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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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PRELIMINARY DESIGN OF A HYDROGEN-COOLED IN-PILE LOOP FOR THE EGCR

Description: A discussion is presented concerning the preliminary design and hazards evaluation of a H-cooled in-pile experimental loop for operation in the large double-walled through-tube in the Experimental Gas-Cooled Reactor (EGCR) at Oak Ridge. This loop is designed to permit experimentation with full-scale fuel element configurations up to 8 in. OD, at inlet gas temperatures of 600 to 950 deg F at 300 psig, and experimental power levels up to 500 kw. The results of a preliminary hazards evaluation ind… more
Date: July 12, 1962
Creator: Michelson, C.; Culp, A.W. & Neill, F.H.
Partner: UNT Libraries Government Documents Department
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System of Automatic Processing and Indexing of Reports

Description: The rapidly increasing volume ot new data in scientific and technical fields demands faster and better ways to communicate the new information to those concerned. A working system. System of Automatic Processing and Indexing of Reports (SAPIR), for doing this is described. SAPIR makes use of the Keyword-in- Context Index principle, by which certain keywords, together with surrounding words that act as modifiers, are selected from the titles of the technical publications. These keywords with the… more
Date: July 12, 1961
Creator: Turner, L. D. & Kennedy, J. H.
Partner: UNT Libraries Government Documents Department
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SELF-LIMITING EXCURSION TESTS OF A HIGHLY ENRICHED PLATE-TYPE D$sub 2$O- MODERATED REACTOR. PART I. INITIAL TEST SERIES

Description: Self-limiting power excursion tests were made to investigate the dynamic response of the Spert II BD-22/24 expanded D/sub 2/O core. This D/sub 2/O- moderated core is comprised of 3-in.-square x 24-in.-long, highly enriched, uranium-aluminum, plate-type fuel assemblies spaced on 6-in. centers. The power excursions were initiated by stepwise reactivity insertions with the system at ambient temperature and atmospheric pressure, with no forced coolant flow, and with approximately a 50-in. D/sub 2/O… more
Date: July 12, 1963
Creator: Grund, J.E.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section C Progress Report for April-May 1960

Description: An economical process was successfully demonstrated in bench-scale continuous equipment for stripping U from amines with ammonium carbonate solution. A continuous countercurrent mixer-settler extraction system was set up for further testing of the process for recovery of Te, Np, and U by tertiary amine extraction from UF/sub 6/ transfer cylinder was solutions. The effect of Purex aqueous feed adjustment procedures on Pu extraction by 1 M di-secbutyl phenylphosphonate (DSBPP) was studied. Work w… more
Date: July 12, 1960
Creator: Brown, K B
Partner: UNT Libraries Government Documents Department
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The Bonding of Molybdenum-and Niobium-Clad Fuel Elements

Description: A solid-state bonding technique involving the use of gas pressure at elevated temperatures was utilized for the self-bonding of molybdenum and niobium. Bonding conditions and surface preparation as a function of the integrity of the bond achieved were evaluated for each material. Optimum self-bonding of niobium was achieved by bonding parameters of 2100 to 2300 deg F at 10,000 psi for 3 hr with surfaces which had been prepared by etching in a nitrichydrofluoric acid solution prior to bonding. T… more
Date: July 12, 1960
Creator: Paprocki, S. J.; Hodge, E. S. & Gripshover, P. J.
Partner: UNT Libraries Government Documents Department
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High temperature coil design

Description: No Description Available.
Date: July 12, 1965
Creator: Donelan, L.
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During May 1960

Description: The investigation of the stabilizing influence of oside additions to UO/ sub 2/ was continued. The effects of fast-neutron irradiation upon the mechanical properties of Type 347 stainless steel are being investigated. Tensile data are reported for alloys of Nb-Cr and Nb-Zr. The major effect of fast-neutron irradiation on the creep properties of Zircaloy-2 is being studied by comparing the in-reactor creep behavior of the alloy with out-of-reactor creep properties. New methods for the determinat… more
Date: July 12, 1960
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Partner: UNT Libraries Government Documents Department
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Residual Radiation of the LRL 184-Inch Cyclotron

Description: Residual radioactivity at the Lawrence Radiation Laboratory 184-Inch Cyclotron was measured during November 1960. The study was conducted along three principal lines: (1) general survey of radiation levels in the cyclotron vault, (2) activation of foils placed near the cyclotron, and (3) gamma-ray spectra of the cyclotron gap region, including dee structure. Initial radiation levels were less than 8 r/hr which dropped to abcut 10 mr/hr after 48 hr. The observed activities induced in copper foil… more
Date: July 12, 1961
Creator: Boom, R. W.; Toth, K. S. & Zucker, A.
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
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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
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