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12-INCH SODIUM FLOW CONTROLLER. Technical Manual 20357

Description: A manual is presented for the Sodium Flow Controller used in controlling flow to regulate heat transfer in a liquid metal nuclear power plant. A description of the controller, general installation and operational pointers, installation instructions, instructions for dismantling of the Sodium Flow Controller, instructions for assembly of Sodium Flow Controller, list of special tools and fixtures, and repair parts list are given. (M.C.G.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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BOILING NUCLEAR SUPERHEATER (BONUS) POWER STATION. Supplementary Study. Extrapolation to Large Central Station Integral Nuclear Superheat Plant

Description: An evaluation was made of the maximum size plant for which the BONUS reactor plant could serve as a realistic prototype and the design changes required to increase the size and characteristics for the present BONUS design such that it could serve as a realistic prototype for the largest feasible integral-superheat reactor power plant. (M.C.G.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report, July, August, September, 1961

Description: Development activities are reported on pyrometallurgical processes including melt refining and those using liquid metal solvents. Development of processing facilities for EBR II is also reported. In other work, laboratory- and engineering-scale investigations on fluoride volatility processes were condueted, and conversion of UF/sub 6/ to UO/sub 2/ was studied. Investigations are also reported concerning the kinetics of metal ignition and oxidation, and metalwater reactions. In work associated w… more
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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Chemical Processing Technology Quarterly Progress Report, January-March 1961

Description: Studies are reported on aqueous zirconium processing, dissolution of BeO- UO/sub 2/ ceramic fuel, the aqueous stainless steel process, the behavior of dibutyl phosphates, use of boron (boric acid) solution to assure critical safety, fluidized bed calcination, conversion of amorphous alumina to alpha alumina, the Demonstrational Waste Calcining Facility, removal of long-lived radioisotopes from waste solutions, separation of iron, nickel, and chromiun from stainless steel waste solutions, electr… more
Date: October 31, 1962
Creator: Bower, J. R.
Partner: UNT Libraries Government Documents Department
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Design and Development of Fast-Response Thermopile-Type Neutron-Flux- Sensitive Device. Final Report, Phase 2

Description: A program was directed toward development of a thermopile-type neutron- flux-sensitive meter of small physical size and having a fast response time (25 msec) and a high signal output. The meter configuration selected consists essentially of a metallic heat sink, a thermopile, and a thin layer of neutron- sensitive material in series. When the meter is exposed to a neutron environment, heat generated in the neutron-sensitive material flows across the thermopile unit to the heat sink. The signal … more
Date: October 31, 1962
Creator: Gee, L. J.
Partner: UNT Libraries Government Documents Department
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DESIGN AND OPERATION OF 1800 F PUMPED BOILING RUBIDIUM LOOP SYSTEM AND DETERMINATION OF DENSITY AND VAPOR PRESSURE RUBIDIUM BETWEEN 174 AND 1800 F. Space Power Systems Technology Studies: Rubidium, Corrosion and Physical Properties Evaluation Program. Final Report (Report No. 16), February 1, 1960 through May 31, 1961

Description: A pumped boiling rubidium loop was designed, operated, and analyzed. The loop simulated some of the characteristics of a boiling rubidium space power conversion system. Such a system would involve either a reactor or heat exchanger as the power source, and a turbine and radiator as the power conversion and vapor condensing equipment. This loop was used to study instrumentation and control problems and effects of rubidium corrosion on containment materials, and to gain some rough physical proper… more
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF CLAD CERAMIC FUEL PLATES BY SPRAY-COATING TECHNIQUES. Quarterly Technical Progress Report, April-June 1961

Description: Studies were made on the effects of spray-coating variables on coating characteristics in the development of plasma-jet spraying techniques for making clad UO/sub 2/ fuel plates. UO/sub 2/ coatings of up to 90% theoretical density and - O/U ratios of nearly 2.00 were deposited at efficiencies of 40%. Adherent UO/sub 2/ coatings up to 0.100 inch thick can be deposited on 0.030-inch thick stainless steel and Zircaloy-2 substrates. Studies of coated composite bends and coating adherence at room te… more
Date: October 31, 1962
Creator: Weare, N. E.; Buchanan, E. & Marchandise, H.
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF CLAD CERAMIC FUEL PLATES BY SPRAY-COATING TECHNIQUES. Quarterly Tecnnical Progress Report, October-December 1960

Description: Activities in a ptogram concerned with development of plasma-jet spray- coating techniques suitable for production of clad ceramic fuel plates are described. Experiments on application of zirconia coatings are also described. A survey of UO/sub 2/ powder was conducted to determine its suitability for plasma spraying. Also conditions were established for spraying fused and milled UO/sub 2/. The effects of process variables on coating and deposition characteristics were found to correlate. Densit… more
Date: October 31, 1962
Creator: Weare, N. E.
Partner: UNT Libraries Government Documents Department
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Development of Isotope Dilution Techniques for Assay of Food Additives

Description: "lsotope dilution techniques are described for the assay of chlorinated hydrocarbon pesticides and organic phosphorus pesticides in foods. Results are given for the determination of tetranitro-DDT-dianilide, dianilide of tetranitro- DDE, dieldrin, systox, and derivatives of these compounds. "
Date: October 31, 1962
Creator: Nuclear Science and Engineering Corporation
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report, April 1 through June 30, 1962

Description: Progress in the development and testing of plutonium fuels is described. Topics covered include: project and facility administration, preparation and characterization of fuel materials, fabrication and evaluation of fuel shapes, fuel element fabrication and evaluation, radiation testing aad evaluation, and reactor physics and engineering parametric studies. (M.C.G.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report for Period January 1 through March 31, 1962

Description: During this reporting period, particular effort was of aced on powder blending and pellet sintering studies prior to irradiation sample fabrication, and, subsequently, the production and characterization of the pellets slated for irradiation. Also, PuO/sub 2/ and UO/sub 2/-PuO/sub 2/ characterization studies were continued, and new techniques are being developed. Specifically, dynamic moisture pickup determinations on PuO/sub 2/ were made in moist air, N, and CO/ sub 2/ atmospheres using a reco… more
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM BEARING FUEL MATERIALS. Progress Report for period July 1 through September 30, 1961

Description: Data are tabulated for the characteristic parameters of PuO/sub 2/ powders prepared by the continuous oxalate precipitation process. The results show that the PuO/sub 2/ surface area decreases almost linearly with calcination hold times at 760 deg C. A thermogravimetric study of the decomposition of Pu oxalate indicate the formation of an initial stable compound at ~ l00 deg C and a stable intermediate at ~ 300 deg C. Characteristic data are tabulated for UO/sub 2/ -5% PuO/sub 2/ and UO/sub 2/-… more
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report, October 1-December 31, 1961

Description: Continued effort is reported on preparation and characterization of PuO/ sub 2/ and UO/sub 2/-- PuO/sub 2/ mixtures. Sintering and characterization of pellets for irradiation tests was emphasized, and efforts were also devoted to plasma torch production of spherical PuO /sub 2/ and coating of oxide materials. PuO/sub 2/ produced by the oxalate process from low concentration feed contains agglomerates which are not readily broken down, while that produced from normal feed contains larger agglome… more
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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ENERGY STORAGE MECHANISMS IN LIQUID HYDROGEN

Description: Section II, Task 1, Item 5 of FZM-2386. Energy-storing molecular products of radiation in liquid H/sub 2/ are examined from the point of view that the expulsion of potertial energy in the form of such products may lead to lower design weights for nuclear rockets. It is found that a significant fraction of the energy deposited by radiation in liquid H/sub 2/ is stored temporarily through the dissociation and excitation of H/sub 2/ molecules. Experimental and theoretical results are consistent wi… more
Date: October 31, 1962
Creator: Carter, H.G.
Partner: UNT Libraries Government Documents Department
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EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report No. 3, April-June 1961

Description: The heat-transfer loop was completed and is in operation. Difficulty was experienced in obtaining a sufficiently strong connection between the burnout- detector voltage tap and the heating element. This problem and its potential solution are described. The lack of means of obtaining controlled burnout prevented collection of data on the burnout effects of the ultrasonic field. (auth)
Date: October 31, 1962
Creator: Romie, F.E.
Partner: UNT Libraries Government Documents Department
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GAUGE FOR MEASURING BOW OF TUBES

Description: A mechanical gage was designed to measure the bow over any one-foot length of long cylindrical material. The gage was used successfully for measuring bow in components of tubular fuel elements at the Savannah River Laboratory. (auth)
Date: October 31, 1962
Creator: Alewine, G.B.
Partner: UNT Libraries Government Documents Department
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IDAHO DIVISION SUMMARY REPORT, APRIL THROUGH SEPTEMBER 1961

Description: Research and development progress is reported on TREAT, BORAX V, ZPR- III, EBR-II, and the reactor operations personnel training program. (M.C.G.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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IDO REPORT ON THE NUCLEAR INCIDENT AT THE SL-1 REACTOR, JANUARY 3, 1961 AT THE NATIONAL REACTOR TESTING STATION

Description: A summary of activities which took place following an incident at the SL- 1 is presented. No attempt to determine the incident cause is included. A brief description of the SL-1 and the operating program in progress prior to the incident is given along with detailed information on various aspects of the past incident developments. (J.R.D.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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INVESTIGATION OF THE TECHNICAL FEASIBILITY OF COLD EXTRUSION FOR ZIRCALOY-2 TUBING PRODUCTION. Quarterly Technical Progress Report, July-September, 1961

Description: Bar-extrusion tests were performed at 50. 65, and 80% reductions at room temperature and 300 deg C. Tensile tests were conducted on as-extruded and heat-treated specimens. The results are tabulated for comparison. The extrusion of small tubing, 0.560-in. OD x 0.030-in. wall, in the first and second tube- extrusion steps are described. (B.O.G.)
Date: October 31, 1962
Creator: Weil, F.E. & Hill, J.G.
Partner: UNT Libraries Government Documents Department
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INVESTIGATION OF THE TECHNICAL FEASIBILITY OF COLD EXTRUSION FOR ZIRCALOY-2 TUBING PRODUCTION. Quarterly Technical Progress Report No. 3, April-June 1961

Description: Investigations are being made to establish the feasibility of using cold extrusion to produce Zircaloy-2 tubular products. Tests on extruding 1 1/4-in. diameter billets were completed. Samples in 46 bar-extrusion tests were extruded with 80% reduction at 400 deg C. Severe lubricant breakdown occurred. Piercing tests were conducted at, room temperature and 200 deg C, using 50% reduction and a 140-degree conical punch profile. Good extrusions were obtained in forraing 1.07-in. OD x 0.052-in. wall… more
Date: October 31, 1962
Creator: Weil, F.E. & Hill, J.G.
Partner: UNT Libraries Government Documents Department
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INVESTIGATION OF THE TECHNICAL FEASIBILITY OF COLD EXTRUSION FOR ZIRCALOY-2 TUBING PRODUCTION. Quarterly Technical Progress Report, October-December 1960

Description: S>Activities included completion of room-temperature extrusion tests on Zircaloy bar, and extrusions with 50% reduction at temperatures up to 400 deg C. Results of these tests are tabulated along with results of billet piercing tests at 300 deg C. It is noted that production of capped Zircaloy tubes by cold extrusion appears promising. (J.R.D.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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