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PATHFINDER ATOMIC POWER PLANT STEAM SEPARATOR DEVELOPMENT

Description: Development of a steam separator the Pathfinder Reactor is reported. A full-scale separator model was developed through the combination of scale-model testing and the application of principles associated with the existing theory of centrifugal separation. This model was put through full-scale air-water tests which led to modifications and a final design which meets Pathfinder requirements. Design data are included for the reactor and the steam separator. (J.R.D.)
Date: June 15, 1962
Creator: Kutsch, G. C.; Swanson, D. H. & Yant, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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COMPILER INTO GEORGE ASSEMBLY ROUTINE

Description: This program of the GEORGE Assembly Routine (GAR) will accept Fortran- like statements from paper tape and create the GAR language program on tape. This includes the needed calls for common subroutines and the reservations for the named variables and temporaries. The original statements in Fortran are carried along as remarks. The GAR language program may then be processed in the usual way by the GEORGE Assembly Routine, giving machine-language code. The level of sophistication of the source la… more
Date: June 1, 1962
Creator: George, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Seismic Vibrations on the Experimental Gas-Cooled Reactor

Description: The effects of seismic vibrations on the dynamic behavior of a composite system were analyzed. The equations of motion were derived and soIved with special emphasis on determining the resulting stresses. The method of analysis thus developed was applied to the composite structure consisting of the core, pressure vessel, and supporting skirt of the Experimental Gas-Cooled Reactor (EGCR). A system with three degrees of freedom was considered in order to determine the effects of an earthquake of t… more
Date: June 22, 1962
Creator: Witt, F.J.; Carver, D.R. & Maxwell, R.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pathfinder Atomic Power Plant Technical Progress Report, January 1962-March 1962

Description: S>Progress is reported on the research and development program being performed in connection with the design of the Pathfinder Atomic Power Plant. The topics covered include: fuel material cladding, bonding, and irradiation testing; heat transfer and fluid flow; fuel element manufacturing research and development; low-enrichment superheater fuel element design; mechanical studies of control rods, guide tubes, and control rod drives; reactor physics; and reactor and system dynamics. (C.H.)
Date: June 30, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Propane Vibrational Analysis

Description: Using the group vibratibn method of McMurry, the normal frequencies and coordinates of propane and three of its symmetrical deuterium substituted compounds were obtained. The force constants used were taken from a variety of previous works on hydrocarbons. The results give reasonable agreements with the experimental frequency and mode assignments of others. (auth)
Date: June 12, 1962
Creator: Marshall, G. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Status Report on LAMPRE Program for Period Ending May 20, 1962

Description: During the report period 110 Mw-hr of operation were completed by LAMPRE I at various power levels, and observations were made of control element performance and reactivity losses. Metallographic examination of a Core I capsule having 120 Mw-hr of irradiation exposure disclosed no major attack. Core II utilizes Ta alloy melts and 13 fuel melts. Starting materials for Core II capsules are tabulated. In research and development a gamma-ray conversion television was used to observe the flow of mol… more
Date: June 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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REPORT ON GLOVE BOXES AND CONTAINMENT ENCLOSURES

Description: Criteria and guide lines are presented for the design, construction, and operation of safe, economical, and efficient glove boxes and associated facilities based upon present conditions and anticipated changes. Comprehensive discussion of glove box materials and components, safety and fire prevention methods, health physics problems, operational considerations, and brief descriptions of AEC installations are included. (39 references) (C.H.)
Date: June 20, 1962
Creator: Garden, N.B. ed.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Improved Sample Bonding and Emission With Tantalum Surface Ionization Filaments

Description: Techniques for conditioning of Ta filaments for improved bonding and emission with a Ta metal powder-Ta/sub 2/O/sub 5/ mixture are described. A porous Ta metal layer is deposited which restricts sample to the filament. Metal- oxide ion emission is enhanced with additional Ta/sub 2/O/sub 5/ to the porous layer. Reduction of fractionation through action of liquid Ta/sub 2/O/sub 5/ is discussed in particular for Sr+ emission. Use of conditioned filaments for rapid U concentration analysis with a s… more
Date: June 29, 1962
Creator: Goris, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FUEL CYCLE DEVELOPMENT PROGRAM. Quarterly Progress Report, January 1 to March 31, 1962

Description: The permanent shutdown of the Westinghouse Testing Reactor at the end of the quarter forced a revision in plans for programming the remainder of the irradiation of the two uninstrumented capsules whose testing was in progress. The minimum estimated burnup at this point, based on hot cell data obtained from the pilot capsule, was 13,100 MW-d/ton U. It was decided to continue the testing of only one capsule in another reactor until the original goal of 20,000 MW-d/ton U is reached. The irradiatio… more
Date: June 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Primary Shield Optimization Survey for the PL-3 Reactor

Description: A detailed study of four reactor and shield configurations was made. Two basic reactor types, the boiling water and pressurized water reactors were considered. Shield materials of lead-water and iron-water were used with varying thicknesses for determining the optimum shield configuration for the PL-3 reactor. Also presented is a survey of available shielding codes. (auth)
Date: June 28, 1962
Creator: Scoles, J. F. & Crouch, A. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A PULSED EDDY CURRENT TEST SYSTEM USING REFLECTED FIELDS

Description: An eddy current test system is described in which the test information is detected as a series of fields reflected from the metal surface and interior. Pulsed electromagnetic fields are caused to impinge upon the test specimen. These fields are restricted to a small cross sectional area over a path in space long enough to be useful for test purposes by devices called mask-apenture assemblies. This approach provides a number of advantages over conventional eddy current methods of comparable capa… more
Date: June 11, 1962
Creator: Renken, C. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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FEASIBILITY OF Pu$sup 239$-U$sup 235$-FUELED CORES TO PREDICT Pu$sup 239$- FUELED CORE DIMENSIONS

Description: Use of Pu/sup 239/ -- U/sup 235/-fueled fast critical assemblies to estimate properties of Pu/sup 239/-fueled assemblies is of interest because of safety considerations and limited plutonium availability. Bare and reflected homogeneous cores and reflected two-region cores are considered. The fuel, 5% by volume, is assumed to be Pu/sup 239/ and U/sup 235/ of various fuel composition ratios for the homogeneous cores. For the tworegion cores the 5% fuel volume is Pu/sup 235/ in the central region … more
Date: June 1, 1962
Creator: Meneghetti, D. & Ishikawa, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART III. STAINLESS STEEL (304) IN NITRATE SOLUTIONS

Description: The potential-current density relationships for 304 stainless steel dissolution in a nitrate system were studied as a function of solution composition and temperature in order to optimize the conditions for electrolytic dissolution of ihis material. In the nitrate system, the anodic dissolution of steel takes place in the transpassive region. Under some conditions, deviations from Tafel behavior are observed which depend greatly on the nitrate and hydrogen ion concentration, and on temperature.… more
Date: June 1, 1962
Creator: Aylward, J. R. & Whitener, E. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal Stress Testing of Type 1 Fuel Plates

Description: Thermal stress tests on Type 1, SM-1A Core II fuel ele-ment sections were performed to study plate distortion and determine its dependency on temperature distribution, temperature differential, initial flatness, and ripple length. Test results will be correlated with the analytical model and used to predict ripple growth in other plate-type fuel elements. The tests showed that ripple growth is dependent on initial flatness of the plate and that the characteristic shape of ripples is maintained … more
Date: June 27, 1962
Creator: Gebhardt, F. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spert I Destructive Test Program Safety Analysis Report

Description: The water-moderated core used for destructive experiments is mounted in the Spent I open-type reactor vessel, which has no provision for pressurization or forced coolant flow. The core is an array of highly enriched aluminum clad, plate-type fuel assemblies, using four bladetype, gang-operated control rods. Reactor transients are initiated at ambient temperature by step-insentions of reactivity, using a control rod which can be quickly ejected from the core. Following an initial series of stati… more
Date: June 15, 1962
Creator: Spano, A. H. & Miller, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ECONOMIC FACTORS OF MFP THERMOELECTRIC GENERATORS. Interim Report

Description: Mixed Fission Products (MFP) for use as a heat source for thermoelectric generators will become increasingly available in the coming years. The Atomic Energy Conamission sponsored program on solidification of nuclear wastes is now entering the hot-bench scale test phase. During this phase approximately 5000 thermal watts of two year old MFP could be produced monthly. Two different types of hot calcination pilot plants are planned for installation at the Hanford National Laboratories in the 1964… more
Date: June 1, 1962
Creator: Barmat, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Secondary Isotope Effects in Molecular Structure

Description: A study was made to determine whether secondary iso tope effects also occur in molecular structure. Electron diffraction studies were carried out on ethane and deuteroethane. In C/sub 2/H/sub 6/ the mean C-C and C-H bond lengths found agreed very closely with values determined for other paraffin hydrocarbons, and the C--H bond showed a normal primary isotope effect (~ 0.005 A) similar to that found in methane when H is replaced by O. The output of the leastsquares analysis suggested that the me… more
Date: June 15, 1962
Creator: Bartell, L. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JANUARY-MARCH 1962

Description: Additional experiments conducted on nitridation of irradiated U-fissium fuel pins revealed that irradiation does not greatly affect the nitridation rate at 300 deg C. In skullreclamation development, a phase separation common to both the blanket- and skull-processes was investigated in which a 50% Mg-- Zn supernatant solution was removed from precipitated U metal. In most runs the supernatant phase was removed with negligible U entrainment. The reduction rate of ZrO by Zn--Mg solution under sku… more
Date: June 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Behavior of Restrained and Vented Uranium-2 w/o Zirconium Alloy. Final Report-Programs 6.1.22 and 6.1.27

Description: Twelve 0.22-in.-diameter fuel specimens containing a longitudinal central vent and clad with 0.010 in. of Type 304 stainless steel were irradiated to evaluate the effect of restraint and a central vent on fuel element stability. The cladding of 10 of the specimens contained porous end plugs to vent any released fission gas and thus to minimize the buildup of gas pressure within the stainless steel cladding. The specimens consisted of a 20% enriched uranium--2 wt% zirconium alloy core surrounded… more
Date: June 1, 1962
Creator: Horak, J. A.; Kittel, J. H. & Yaggee, F. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Technology Quarterly Progress Report, January-March 1962

Description: The processing of Al fuel, principally of the MTR-ETR type, is reported. Processing rate averaged 90% of flow sheet values for the entire operating period, and a U recovery of 99.85% was achieved. Aqueous Zr fuel processing studles continued with the objective of adapting the HF process to continuous dissolution-complexing in order to increase the capacity of the ICPP process while using as much existing equipment as possible to minimize costs. Good results were indicated in a 190-hr run dissol… more
Date: June 29, 1962
Creator: Bower, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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