529
529
Jul 11, 2010
07/10
by
NON
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No Abstract Available
Topics: REACTOR CORES, REACTOR DESIGN, PRODUCTION ENGINEERING, REACTOR MATERIALS, REACTOR TECHNOLOGY,...
431
431
Jun 15, 2011
06/11
by
Kliore, A
texts
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No Abstract Available
Topics: SPACE POWER REACTORS, THERMIONIC CONVERTERS, THERMIONIC POWER GENERATION, MATERIALS TESTS, PRODUCT...
Topics: DTIC Archive, Cadwell, J J, HANFORD ATOMIC PRODUCTS OPERATION RICHLAND WA, *METALLURGY, *REACTOR...
1,379
1.4K
Jun 15, 2011
06/11
by
NON
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No Abstract Available
Topics: COOLING SYSTEMS, NUCLEAR FUEL ELEMENTS, TUNGSTEN, WATER MODERATED REACTORS, REACTOR MATERIALS,...
261
261
Jul 11, 2010
07/10
by
YAKOVLEV, N. A.; ALPEROVICH, Y. A.; SKUVLOVA, N. V
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No Abstract Available
Topics: MARS LANDING, NUCLEAR PROPULSION, NUCLEAR REACTORS, SPACECRAFT PROPULSION, NUCLEAR ELECTRIC POWER...
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400
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No Abstract Available
Topics: CHEMICAL ANALYSIS, SPACE POWER UNIT REACTORS, TUNGSTEN COMPOUNDS, URANIUM OXIDES, COMPOSITE...
Topics: DTIC Archive, Dillon, I. G., ARGONNE NATIONAL LAB IL, *REACTOR FUELS, *FISSION PRODUCTS, *BREEDER...
225
225
Jul 12, 2010
07/10
by
Bunce, R. C
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The triangle (antenna) scan (TRISCAN) is a method of improving the alignment between the boresight of the Deep Space Network antennas and a particular target, spacecraft, or radio source (star). For stars, the method works in conjunction with the noise adding radiometer and the antenna pointing system to form estimates of the alignment offset coordinates. This information is then used to position the antenna for improved target alignment. A comparison with CONSCAN is included since a CONSCAN...
Topics: ALKALI METALS, SILICON TETRACHLORIDE, CHEMICAL REACTORS, HALOGEN COMPOUNDS, PRODUCTION ENGINEERING,...
331
331
May 6, 2010
05/10
by
Conway, J. B.; Muehlenkamp, G
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Materials for nuclear propulsion systems in space
Topics: LECTURES, MODERATORS, NUCLEAR PROPULSION, NUCLEAR REACTORS, PROPULSION SYSTEM CONFIGURATIONS,...
427
427
Jun 21, 2010
06/10
by
Dobrev, D.; Lefterov, D.; Ruskov, T.; Tomov, T
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Mossbauer cobalt 57 isotope source incorporated into palladium crystal lattice
Topics: RADIATION SHIELDING, REACTOR DESIGN, SIZE DETERMINATION, SPACE POWER UNIT REACTORS, PAYLOADS,...
A three-dimensional finite elements analysis is reported of the nonlinear behavior of PCRV subjected to internal pressure by comparing calculated results with test results. As the first stage, an analysis considering the nonlinearity of cracking in concrete was attempted. As a result, it is found possible to make an analysis up to three times the design pressure (50 kg/sqcm), and calculated results agree well with test results.
Topics: NASA Technical Reports Server (NTRS), CONCRETES, CRACKING (FRACTURING), FINITE ELEMENT METHOD,...
346
346
Jun 20, 2010
06/10
by
Brehm, R. L
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Temperature coefficients of reactivity due to Doppler broadening of resonances in materials for in-pile thermionic reactor materials
Topics: COEFFICIENTS, DOPPLER EFFECT, TEMPERATURE MEASUREMENT, THERMIONIC REACTOR, DOPPLER EFFECT,...
This report, GEMP-1004, is the seventh annual report on the unclassified portion of the GE-NMPO Fuels and Materials Development Program conducted during calendar year 1967 under Contract No. AT(40-1)-2847. This report covers eleven unclassified jobs: (1) properties of reactor materials from 1000 deg to 3000 deg C (2) radiation effects on the time-, temperature, and stress-dependent properties of fast breeder reactor (FBR) cladding and structural materials; (3) fabrication of FBR advanced fuel...
Topics: DTIC Archive, GENERAL ELECTRIC CO PLEASANTON CA NUCLEAR TECHNOLOGY DEPT, *REACTOR MATERIALS,...
The operation of the White Sands Missile Range Fast Burst Reactor is discussed. Space radiation studies in radiobiology, dosimetry, and transient radiation effects on electronic systems and components are described. Proposed modifications to increase the capability of the facility are discussed.
Topics: NASA Technical Reports Server (NTRS), NUCLEAR REACTORS, REACTOR DESIGN, REACTOR MATERIALS, REACTOR...
350
350
May 27, 2011
05/11
by
Hurrell, Herbert G
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A concept of combustion time lag that includes dependency on injection velocity is introduced. The concept is used in the formulation of chamber transfer functions and in an analysis of low-frequency combustion instability. Theoretical frequency responses and stability boundaries are compared with those obtained when the injection-velocity effect on the time lag to be an important consideration, in the theory of chamber dynamics and combustion instability
Topics: REACTOR MATERIALS, CONTAINMENT, LIQUID COOLING, NASA PROGRAMS, HAZARDS, NUCLEAR ELECTRIC POWER...
An improved material for use in a catalytic reactor which reduces nitrogen oxide from internal combustion engines is in the form of a zirconium-modified, precipitation-strengthened nickel-copper alloy. This material has a nominal composition of Ni-30 Cu-0.2 Zr and is characterized by improved high temperature mechanical properties.
Topics: NASA Technical Reports Server (NTRS), COPPER ALLOYS, NICKEL ALLOYS, REACTOR MATERIALS, ZIRCONIUM,...
Several candidate alloys and coatings were evaluated for use in automobile thermal reactors. Full-size reactors of the candidate materials were evaluated in cyclic engine dynamometer tests with a peak temperature of 1040 C (1900 F). Two developmental ferritic-iron alloys, GE-1541 and NASA-18T, exhibited the best overall performance by lasting at least 60 percent of the life of test engine. Four of the alloys evaluated warrant consideration for reactor use. They are GE-1541, Armco 18 SR,...
Topics: NASA Technical Reports Server (NTRS), AUTOMOBILE ENGINES, IRON ALLOYS, THERMAL REACTORS,...
An exploratory out-of-reactor investigation was made of the effects of short-time temperature excursions above the nominal operating temperature of 990 C on the compatibility of advanced nuclear space-power reactor fuel pin materials. This information is required for formulating a reliable reactor safety analysis and designing an emergency core cooling system. Simulated uranium mononitride (UN) fuel pins, clad with tungsten-lined T-111 (Ta-8W-2Hf) showed no compatibility problems after heating...
Topics: NASA Technical Reports Server (NTRS), NUCLEAR FUELS, SPACE POWER REACTORS, TEMPERATURE EFFECTS,...
Lithium hydride is recommended for neutron attenuation and depleted uranium is recommended for gamma ray attenuation. For minimum shield weights these materials must be arranged in alternate layers to attenuate the secondary gamma rays efficiently. In the regions of the shield near the reactor, where excessive fissioning occurs in the uranium, a tungsten alloy is used instead. Alloys of uranium such as either the U-0.5Ti or U-8Mo are available to accommodate structural requirements. The...
Topics: NASA Technical Reports Server (NTRS), LITHIUM HYDRIDES, RADIATION SHIELDING, SPACE POWER UNIT...
Materials for a lithium-cooled space power reactor concept must be chemically compatible for up to 50,000 hr at high temperature. Capsule tests at 1040 C (1900 F) were made of material combinations of prime interest: T-111 in direct contact with uranium mononitride (UN), Un in vacuum separated from T-111 by tungsten wire, UN with various oxygen impurity levels enclosed in tungsten wire lithium-filled T-111 capsules, and TZM and lithium together in T-111 capsules. All combinations were...
Topics: NASA Technical Reports Server (NTRS), COMPATIBILITY, HIGH TEMPERATURE RESEARCH, REACTOR MATERIALS,...
Topics: DTIC Archive, OFFICE OF TECHNICAL SERVICES WASHINGTON DC, *NUCLEAR ENERGY, *REACTOR MATERIALS,...
The nuclear reactor shield analysis procedures employed at NASA-Lewis are described. Emphasis is placed on the generation, use, and testing of multigroup cross section data. Although coupled neutron and gamma ray cross section sets are useful in two dimensional Sn transport calculations, much insight has been gained from examination of uncoupled calculations. These have led to experimental and analytic studies of areas deemed to be of first order importance to reactor shield calculations. A...
Topics: NASA Technical Reports Server (NTRS), RADIATION SHIELDING, REACTOR MATERIALS, REACTOR TECHNOLOGY,...
The scaled up chemical reactor for a SiF4-Na reaction system is examined for increased reaction rate and production rate. The reaction system which now produces 5 kg batches of mixed Si and NaF is evaluated. The reactor design is described along with an analysis of the increased capacity of the Na chip feeder. The reactor procedure is discussed and Si coalescence in the reaction products is diagnosed.
Topics: NASA Technical Reports Server (NTRS), CHEMICAL REACTORS, ELECTROCHEMISTRY, SILICON, SODIUM, SOLAR...
Microscopic studies were undertaken to characterize the failure processes and to establish correlations with fatigue crack propagation data of Type A302-B ferritic steel tested in air at room temperature. A cooperative program was established between the Naval Research Laboratory (NRL) and the Centro Informazioni Studi Esperienze (CISE) to investigate the fatigue properties of this ferritic steel for nuclear pressure vessel applications. Failed specimens have been examined by scanning electron...
Topics: DTIC Archive, Gabetta ,G, NAVAL RESEARCH LAB WASHINGTON DC, *STEEL, *CRACK PROPAGATION,...
Neutron-induced increases in the brittle-ductile transition temperature (delta TT) of A302-B pressure vessel steel have been measured from irradiations in a number of reactor environments for neutraon fluences representative of pressure vessel design lifetimes. While these measurements have permitted formulation of the trends necessary for delta TT projections in operating reactors, certain anomalous results have been observed wherein measurements fell outside the nominal limits of the trends....
Topics: DTIC Archive, Serpan, Jr, Charles Z, NAVAL RESEARCH LAB WASHINGTON DC, *DAMAGE, *PRESSURE VESSELS,...
The engineering, design, and fabrication status of the expansion joint unit (EJU) to be employed in the NaK primary coolant piping loop of the 5-kwe Reactor thermoelectric system are described. Four EJU's are needed in the NaK primary coolant piping loop. The four EJU's which will be identical, utilize bellows as the flexing member, are hermetically sealed, and provide double containment. The bellows are of a nested-formed design, and are to be constructed of 1-ply thickness of 0.010-in....
Topics: NASA Technical Reports Server (NTRS), COOLING SYSTEMS, JOINTS (JUNCTIONS), SNAP, SYSTEMS...
The present work was undertaken as part of the research being done in the design of a nuclear reactor for the Navy. Interest is centered on zirconium because of its low neutron absorption and high corrosion resistance thus making it useful for cladding and various structural parts in a reactor. The addition of tin to zirconium in proper amounts, produces an alloy with a higher resistance to corrosion than zirconium alone. Various specimens of polycrystalline zirconium and zirconium-tin alloys...
Topics: DTIC Archive, Moskowitz, Marvin, SYLVANIA ELECTRIC PRODUCTS INC BAYSIDE NY, *THERMAL EXPANSION,...
A description of two Soviet water-moderated-water cooled reactors (VVR-M) is presented, one of which is located in Leningrad and the other in Kiyev. These VVR-M reactors were developed from the prototype VVR-M reactor. Background information, general construction details, features of the control and safety systems, heat transfer characteristics, reactor physics, and the experimental facilities afforded by the reactor are presented. The report is illustrated with cross-section views,...
Topics: DTIC Archive, LIBRARY OF CONGRESS WASHINGTON DC AEROSPACE INFORMATION DIV, *RESEARCH FACILITIES,...
This report is the unclassified portion of the nineteenth in a series of monthly reports of the work in process on materials development for the Atomic Energy Commission under Contract AT(40-1)2847. Included is a summary of the work from October 15, 1962, to December 15, 1962, on three of the fourteen specific development programs in process. Five of the remaining programs are reported in the classified portion of this report, GEMP-19, Part B. The other six, involving the development of ceramic...
Topics: DTIC Archive, GENERAL ELECTRIC CO CINCINNATI OH NUCLEAR MATERIALS AND PROPULSION OPERATION,...
Two new polyethylene cable insulations have been formulated for nuclear applications and have been tested under gamma radiation. Both insulations are based on low density polyethylene, one with PbO and the other with Sb2O3 as additives. The test results show that the concept of using inorganic antioxidants to retard radiation initiated oxidation (RIO) is viable. PbO is more effective than Sb2O3 in minimizing RIO.
Topics: NASA Technical Reports Server (NTRS), ANTIOXIDANTS, ELECTRICAL INSULATION, OXIDATION RESISTANCE,...
This report presents the status of observations at the U. S. Naval Research Laboratory on the embrittlement of steels which are commonly used for the primary pressure containment vessels of nuclear power plants. The demonstrated criterion of nil ductility transition (NDT) temperature provides the basis for meaningful analysis of neutron-induced embrittlement in reactor steels. Results to date indicate that the degree of embrittlement depends upon the material, the nuetron exposure, and the...
Topics: DTIC Archive, Steele, L E, NAVAL RESEARCH LAB WASHINGTON DC, *PRESSURE VESSELS, *REACTOR MATERIALS,...
This is the sixth in a series of quarterly reports summarizing the use of the Naval Research Laboratory Cyclotron Facility. During the six month period ending March 31, 1979, the cyclotron was used in support of six research programs for a total 930 hours of beam on target. These research programs are summarized in this report together with the details of beam time usage and facility engineering. No major operational problems were encountered. (Author)
Topics: DTIC Archive, Bondelid,Rollon O, NAVAL RESEARCH LAB WASHINGTON DC, *CYCLOTRONS, ELECTRONIC...
The effects were studied of a thin tungsten liner on the tensile properties of T-111 tubing considered for fuel cladding in a space power nuclear reactor concept. The results indicate that the metallurgically bonded liner had no appreciable effects on the properties of the T-111 tubing. A hot isostatic pressing method used to apply the liners is described along with a means for overcoming the possible embrittling effects of hydrogen contamination.
Topics: NASA Technical Reports Server (NTRS), HOT ISOSTATIC PRESSING, ISOPYCNIC PROCESSES, PIPES (TUBES),...
The high-temperature crack-growth behaviour of Nimonic PE16 has been studied at 650 deg C under cyclic, static, and combined loads, and the results are compared with those of alloy 718. Crack-growth rates in vacuum under continuous cycling are the same in both alloys but the rates differ significantly in air. A 1 min hold has no effect on the growth rate of fatigue cracks in Nimonic PE16, but has a large effect in Alloy 718 in air. This difference is due to the difference in their...
Topics: DTIC Archive, Sadananda, K, NAVAL RESEARCH LAB WASHINGTON DC MATERIALS SCIENCE AND TECHNOLOGY DIV,...
A series of central core and core-reflector interface sample replacement experiments for 16 materials performed in the NASA heavy-metal-reflected, fast spectrum critical assembly (NCA) were analyzed in four and 13 groups using the GAM 2 cross-section set. The individual worths obtained by TDSN and DOT multidimensional transport theory calculations showed significant differences from the experimental results. These were attributed to cross-section uncertainties in the GAM 2 cross sections....
Topics: NASA Technical Reports Server (NTRS), FAST NUCLEAR REACTORS, REACTIVITY, REACTOR MATERIALS,...
Due to temperature, reactors in operation cause heat and moisture flows in the thick walled prestressed pressure vessels. These flows were studied in three beams of concrete made with crushed limestone aggregate, and in three beams made of crushed gravel/sand aggregate. The flow phenomena were related to the structural development of the concrete by determining the amount of non-evaporatable water, the total porosity, and the pore size distribution. Local temperature and moisture conditions...
Topics: NASA Technical Reports Server (NTRS), ATMOSPHERIC TEMPERATURE, CONCRETES, HEAT TRANSMISSION,...
Upon the shutdown of the organic moderated reactor experiment (OMRE) at the National Reactor Testing Station in Idaho, a program was initiated to determine the total neutron dosage and radiation induced transition temperature increase to the pressure vessel and upper grid plates. Drillings were made across the grid plate and the chips were collected from each position to determine the cross-plate neutron exposure gradient. Drillings were taken and collected from the pressure vessel at the fuel...
Topics: DTIC Archive, NAVAL RESEARCH LAB WASHINGTON DC, *NEUTRON COUNTERS, *ORGANIC MODERATED REACTORS,...
Examinations of the inside surface of irradiated fuel cladding from two reactors show the Zircaloy cladding is exposed to a number of aggressive substances, among them iodine, cadmium, and iron-contaminated cesium. Iodine-induced stress corrosion cracking (SCC) of well characterized samples of Zircaloy sheet and tubing was studied. Results indicate that a threshold stress must be exceeded for iodine SCC to occur. The existence of a threshold stress indicates that crack formation probably is the...
Topics: NASA Technical Reports Server (NTRS), CRACK INITIATION, METAL SURFACES, NASA PROGRAMS, NUCLEAR...
Research programs in physical metallurgy and solid state physics in three research laboratories in Italy are described. Two not-for-profit laboratories and one university laboratory are included.
Topics: DTIC Archive, Lipsitt, Harry A, OFFICE OF NAVAL RESEARCH LONDON (UNITED KINGDOM), *METALLURGY,...
Nuclear reactor pressure vessel materials are subject to progressive reductions in fracture resistance in service due to neutron irradiation. Current technology is insufficient to quantitatively predict radiation embrittlement for all typical materials and their metallurgical variations for neutron fluences of interest. Another needed refinement to radiation effects technology involves the establishment of a relationship between apparent notch ductility and fracture toughness in the irradiated...
Topics: DTIC Archive, Hawthorne,J R, NAVAL RESEARCH LAB WASHINGTON D C, *EMBRITTLEMENT, *NUCLEAR REACTORS,...
Methods are described for electroplating nickel on zirconium and zirconium-tin alloys with as-plated adhesion greater than 6,000 psi, and heat treating to produce alloy-diffusion bonds of 50,000 psi. This supplements the results previously reported (BMI-707). Other metals can be electroplated over nickel, diffusion bonded to the zirconium or zirconium alloy. A method of preparing zirconium for tin, lead-tin-solder, and silver- solder coating is also described. Other metals can be...
Topics: DTIC Archive, Schickner, W. C., BATTELLE MEMORIAL INST COLUMBUS OH, *DIFFUSION BONDING,...
The feasibility of using continuous high-temperature reactions of alkali metals and silicon halides to produce silicon in large quantities and of suitable purity for use in the production of photovoltaic solar cells was demonstrated. Low pressure experiments were performed demonstrating the production of free silicon and providing experience with the construction of reactant vapor generators. Further experiments at higher reagent flow rates were performed in a low temperature flow tube...
Topics: NASA Technical Reports Server (NTRS), ALKALI METALS, CHEMICAL REACTORS, HALOGEN COMPOUNDS,...
This document is the eleventh and final report of a series of summaries of the use and development of the NRL 5-MV Van de Graaff accelerator and associated equipment. The first six were semiannual summaries; and the next five (including the present one) were annual summaries. The present report includes a section on facility development and improvement, including specific reports on (1) the development of new species of ion beams from the Van de Graaff and (2) the construction of a new 200-kV...
Topics: DTIC Archive, Butler,J W, NAVAL RESEARCH LAB WASHINGTON D C, *VAN DE GRAAFF GENERATORS, SILICON...
The reaction kinetics and structures of the alloy/oxide composite system were determined for martensitic and several Widmanstatten-structured alloys oxidized at 300, 400, and 500C in oxygen at 1 atm pressure. At 300 and 400C, there was little difference between the oxidation rates of the differently structured alloys in the early stages of the reaction. Prolonged exposures illustrated the occurrence of two limiting oxidation curves: martensitic specimens oxidized most rapidly, the oxidation...
Topics: DTIC Archive, Cowgill, M G, MCMASTER UNIV HAMILTON (ONTARIO) DEPT OF METALLURGY AND METALLURGICAL...
Alloy 718 is a commercial, wrought nickel-base alloy widely utilized in moderate temperature structural applications and has been proposed for use in advanced nuclear systems. In such applications, Alloy 718 will experience the combined effects of cyclic and static loading and sustained elevated temperatures. However, when used in structures requiring welds, Alloy 718 exhibits reduced weld ductility and strain age cracking when given conventional post-weld duplex age heat treatments. A modified...
Topics: DTIC Archive, Smith,H H, NAVAL RESEARCH LAB WASHINGTON D C, *HEAT TREATMENT, *NICKEL ALLOYS,...
A nickel, silicon and niobium-rich phase observed in heavy ion and neutron-irradiated FV548 steel has been identified as G-phase. It is suggested that the precipitation of nickel and silicon rich phases in austenitic steels during irradiation could reduce the efficiency of silicon as a void swelling inhibitor and may even have a deleterious effect on the long term swelling behaviour of high silicon casts. (Author)
Topics: DTIC Archive, Williams,T M, ATOMIC ENERGY RESEARCH ESTABLISHMENT HARWELL (ENGLAND), *FOREIGN...
Practical application of plasma chemistry to the development of inorganic materials using both low temperature and warm plasmas are summarized. Topics cover: the surface nitrification and oxidation of metals; chemical vapor deposition; formation of minute oxide particles; the composition of oxides from chloride vapor; the composition of carbides and nitrides; freezing high temperature phases by plasma arc welding and plasma jet; use of plasma in the development of a substitute for petroleum;...
Topics: NASA Technical Reports Server (NTRS), CHEMICAL REACTIONS, GAS-METAL INTERACTIONS, INORGANIC...
The effects of three levels of copper content and phosphorus content and two levels of sulfur content on radiation sensitivity and postirradiation heat tratment response were explored for a reactor pressure vessel steel, Type A302-B. Test plates for the investigation were produced from 182-kg (400-lb) laboratory melts. The contributions of individual elements were assessed from Charpy-V (C sub v) notch ductility changes with 288 C (550 F) irradiation and with a 343 C (650 F)-168 h...
Topics: DTIC Archive, Hawthorne,J R, NAVAL RESEARCH LAB WASHINGTON DC, *STEEL, *NEUTRON IRRADIATION,...
Postirradiation heat treatment (annealing) is being investigated as a method for the alleviation of radiation embrittlement to reactor vessel steels. Objectives of this study were to identify those service and metallurgical variables which can affect annealing response, to report data comparisons available for qualification of suspected influences, and to survey experimental results from commercially produced reactor materials and duplicate materials from the laboratory. Twelve factors are...
Topics: DTIC Archive, Hawthorne,J R, NAVAL RESEARCH LAB WASHINGTON DC, *ANNEALING, *REACTOR MATERIALS, *LOW...
The extent and trend of Charpy-V (C sub v) notch ductility changes in reactor vessel materials with fluences of 1 X 10 (TO THE 18TH POWER) TO 10 X 10 (to the 18th power) n/square cm greater than 1 MeV were investigated with several thick section steel plates and submerged arc weld deposits irradiated at 288C (550 F). The materials were fully representative of reactor vessels now in service and had copper contents ranging from 0.10 to 0.40% and phosphorus contents ranging from 0.008 to 0.020%....
Topics: DTIC Archive, Hawthorne,J R, NAVAL RESEARCH LAB WASHINGTON DC, *NUCLEAR REACTORS, *STRUCTURAL...
