Office of Scientific & Technical Information Technical Reports - 83 Matching Results

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241-SX tank farm waste storage

Description: Salt wastes from the Redox solvent extraction process have been routed to the 241-SX tank farm for storage since May 21, 1954. Tanks in this farm contain wastes from three types of irradiated uranium processing: (1) low (approximately 250 MWD/T) and (2) high (approximately 600 MWD/T) natural uranium; and (3) E-metal. It is estimated that approximately 1.6 Kgs of Am-Cm, 17 Kgs of Np-237, 20 Kgs of Pu and 8 tons of uranium are present in the sludges from wastes generated through 4-30-64. A total … more
Date: September 3, 1964
Creator: Hanson, G. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Adhesives, fillers & potting compounds: Special report molecular weight determinations of dimethypolysiloxane polymers

Description: Using a Mechrolab Vapor Phase Osmometer and a Hallikainen Automatic Membrane Osmometer the number-average molecular weight of two samples of dimethylpolysiloxane - 2300 and 8000 cstk - as well as samples made by mixing the two previously mentioned materials were determined.
Date: September 3, 1968
Creator: Luthey, Z. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Adsorption of Activated Nitrogen

Description: The information obtained in this experiment was deduced by measuring the pumping speed as a function of the energy of the incident electrons and as a function of the energy which ions hit the surface.
Date: August 3, 1963
Creator: Donaldson, E E; Winters, H F & Horne, D E
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis of P&W NJ-18A Power Plant Pressure Drop Between Compressor Discharge and Turbine Inlet

Description: This study is part of an evaluation of the P&W NJ- 18A powerplant. The work presented here specifically estimates the pressure drop between the compressor discharge and the turbine inlet. Analysis was asked for two operating conditions. One was for sea level sprint at a Mach no. of 0.9, while the other was for a Mach no. of 0.9 at 35000 ft.
Date: January 3, 1961
Creator: Casagrande, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of test data on ablation of SNAP 2/10A fuel, aluminum, and stainless steel in an arc-heated wind tunnel

Description: A series of arc-jet tests were performed for the purpose of investigating the behavior of SNAP 2/10A fuel in a simulated reentry environment. The data from the tests (motion pictures and transient temperature distributions) were analyzed and compared with computations which used an energy balance to describe the heating of the fuel to its melting temperature. The dissociation of hydrogen was assumed to occur as an isothermal, endothermic phase change. This concept neglects the kinetics of diffu… more
Date: November 3, 1964
Creator: Arnold, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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BIO-ORGANIC CHEMISTRY QUARTERLY REPORT. December 1961, January andFebruary 1962

Description: It has been known for a hundred years that formaldehyde polymerizes to carbohydrate substances in alkaline media. Although the reaction has long attracted much attention, only recently has a detailed qualitative analysis of the products been carried out by chromatographic methods. We have started to re-examine this reaction by combining chromatography with radioactive tracer techniques in the hope of refining the quantitative aspects of the analysis. Our particular interest has been to develop … more
Date: April 3, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Crud deposition in KER loops at pH 10 LiOH

Description: One of the problems which may be encountered in the operation of NPR, or of any similar pressurized-water reactor, is the deposition of crud in the reactor core, particularly on the surfaces of the fuel elements. This crud consists primarily of iron oxides resulting from the corrosion of the piping. It has generally been found to deposit preferentially in a radiation field such as is present in the reactor core. Such deposition is undesirable for two reasons. First, the crud will become activat… more
Date: May 3, 1963
Creator: Dickinson, D. R. & Demmitt, T. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design criteria fire and sanitary water modifications

Description: Water for fire and sanitary use in the older reactor areas is provided by pumps located in the 183 building of each particular area. Each area has two electrically driven pumps for normal use and two steam driven pumps in case of power failure. Distribution within an area is through an underground main loop with laterals to buildings and fire hydrants. When the DR, F and H Reactors are deactivated, fire and sanitary water in each area is still necessary for protection of the area and for certai… more
Date: September 3, 1964
Creator: Steele, C. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design criteria for phase II dummy hydraulic core for containment systems experiment reactor simulator

Description: The design of a Phase II dummy hydraulic core for the CSE reactor simulator is described. The core will be a scale model having features typical of PWR or BWR reactor cores, and will include control rods and associated support mechanisms, fuel elements, a thermal shield, top and bottom core guide and support plates, and flow baffles. The core and simulator vessel will be instrumented to provide measurement of temperature, static and differential pressures, forces on core components, and rarefac… more
Date: October 3, 1966
Creator: Henager, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of process tube dimensions on tube life

Description: In recent months, several process tubes installed during 1961 have been removed and examined out-of-pile in connection with Tube Corrosion Monitor Studies.1 Most of the tubes were believed to be uniform-wall .080in.-nominal-rib-height tubes. The ex-reactor dimensional measurements obtained near the inlet flange showed,that the tubes did not have uniform walls or .08011 nominal rib heights. Subsequently, dimensional measurements were obtained on approximately 200 new process tubes in an effort t… more
Date: December 3, 1962
Creator: Hough, C. G.; Fuller, N. E. & Jensen, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of S8DR chromium diffusion treatment on the creep rupture properties of processed Hastelloy-N tubing

Description: Process development personnel have been seeking means of improving the (after thermal exposure) adhesion of the S8DR ceramic coating to chromized Hastelloy N tubing. This effort has led to the incorporation of an elevated temperature chromium diffusion treatment prior to the application of the ceramic coating. This report describes the results of tests performed to ascertain the influence of the additional thermal treatment on the 1400/sup 0/F creep-rupture properties of S8DR tubing.
Date: June 3, 1967
Creator: Allaria, G.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Hanford Operations on Columbia River temperatures: Interim report No. 2

Description: A research and development project for study of the effects of reactor effluent on Columbia River water quality is being sponsored by the AEC Division of Production. Work was started in October 1962, the first effort being aimed at furnishing an immediate answer to a security question: how closely can Hanford production be estimated by measurement of river temperatures? An interim progress report gave the results of the preliminary investigation. During the calendar year 1963, the study was exp… more
Date: December 3, 1964
Creator: Corley, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effluent plume temperature data

Description: A primary factor in assessing the impact on the biosphere of the discharge of heated reactor effluent to the Columbia River is the degree of initial dilution. Each of the reactor effluent lines discharges at the bottom of the river, approximately normal to the current, and near the main channel. As part of the Division of Production research and development program titled ``The Effects of Reactor Effluent on the Quality of Columbia River Water,`` the temperature measurements recorded in this do… more
Date: June 3, 1968
Creator: Corley, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ETS-1 I&C System cost at completion estimate. Revision B

Description: EG&G submits the following estimated cost at completion of the ETS-1 I&C System as represented by the approved, Reduced Design Package, the SNPO-C letter TSB:AL dated 30 January 1964 and the Approved Program Plan. A summary of this cost estimate and of previous cost estimates, is given. The total cost estimate is $5, 284, 000. While some items have individual costs which differ from those shown in SNPO-C letter of 30 January 1964, the total cost is consistent with that letter. Specifically, the… more
Date: March 3, 1964
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Extrusion of I&E ``O`` size tubing to finalize the process. Experiment No. U-31

Description: Work has been progressing on the development of an extrusion process for I&E tubing. The ultimate object of this development project is to compare the extrusion process from a cost standpoint with, the presently used rolling-drilling process. Various experiments have been performed to determine the optimum billet I.D., the proper follower block technique, the proper tooling parameters for the process, and the proper metallurgical structure of the material for optimum results. This extrusion com… more
Date: February 3, 1961
Creator: Frazier, D.S. & Puterbaugh, J.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FAST FLUX TEST FACILITY CONCEPTUAL SYSTEM DESIGN DESCRIPTION FOR THE BUILDING ELECTRICAL POWER SYSTEM No. 12

Description: The Building Electrical Power System, transmits, distributes and controls the electrical power utilized by the equipment of all of the FFTF system. Included are system functions and design requirements, the physical description of the system, safety considerations, principles of operations, and maintenance principles.
Date: July 3, 1968
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fast Neutron Fluxes in Hanford Reactors

Description: The results of a multi-group, diffusion type code computation for the fast neutron flux distribution in C, K, and N reactors are presented. Relative Ni activations in conjunction with the calculated neutron spectra are used to obtain values for the integrated fast flux per MWD/AT for C and K reactors. The relative, theoretical, integrated fast flux values at the same adjacent fuel powers in C, K, and N reactors in the mid-plane of the filler layers are: (1) C = 1.0; (2) K = 1.3; and (3) N = 2.6… more
Date: May 3, 1960
Creator: Yoshikawa, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final report B, D, F reactor side shield hole boring technology

Description: Four years of intermittent development has culminated in the successful test drilling on-reactor, of one step plug hole. Since 1960, several different drive units and many diamond, carbide, and tool steel cutting heads were tried unsuccessfully in attempts to bore a stepped hole in a mockup of B, D, P side shielding. Success was finally achieved in 1963 using a standard horizontal boring mill and tool steel cutters. With slight modifications, this same equipment was successfully used in an on-r… more
Date: February 3, 1964
Creator: Clemans, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Flowsheet for americium recovery and purification

Description: Americium (atomic weight 241) grows into plutonium as a result of the 13-year half-life beta decay of Pu{sup 241}. An appreciable quantity of Am{sup 241} has.grown into the scrap that accumulated following shut-down of the Recuplex facility, and which will be processed during the initial period of operation of the plutonium reclamation facility. Current interests in trans-plutonium research and in isotopic heat sources make it desirable to consider the recovery of this Am{sup 241}. The americiu… more
Date: September 3, 1963
Creator: Szulinski, M. J. & Curtis, M. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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