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in subjects: "Molybdenum Alloys"

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TCT hybrid preconceptual blanket design studies

The conceptual design of a tokamak fusion-fission (hybrid) reactor, which produces electric power and fissile material, has been performed in a cooperative effort between Princeton's Plasma Physics Laboratory (PPPL) and Battelle's Pacific Northwest Laboratories (PNL). PPPL, who had overall project lead responsibility, designed the fusion driver system. Its core consists of a tokamak plasma maintained in the two-component torus (TCT) mode by both D and T beams and having a single null poloidal d… more

Date: January 1, 1978

Creator: Aase, D. T.; Bampton, M. C. C.; Doherty, T. J.; Leonard, B. R.; McCann, R. A.; Newman, D. F. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Repair Welding of Fusion Reactor Components

Recent experimental investigations indicate that the repair welding of irradiated materials containing greater than 1 to 2.5 appm helium leads to catastrophic cracking in the heat affected zone of the weld. The high temperatures and cooling tensile stresses which occur during the welding process lead to enhanced helium bubble growth in the heat affected zone region, resulting in catastrophic cracking upon cooling. An investigation is proposed which seeks to determine the effect of stress state … more

Date: May 20, 1992

Creator: Chin, Bryan A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Investigation of joining techniques for advanced austenitic alloys

Modified Alloys 316 and 800H, designed for high temperature service, have been developed at Oak Ridge National Laboratory. Assessment of the weldability of the advanced austenitic alloys has been conducted at the University of Tennessee. Four aspects of weldability of the advanced austenitic alloys were included in the investigation.

Date: May 1, 1991

Creator: Lundin, C. D.; Qiao, C. Y. P.; Kikuchi, Y.; Shi, C. & Gill, T. P. S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Deposition and removal of radioactive isotopes from LMFBR components

The development of an analytical model to describe the production, transport and eventual removal of radioactive materials in the primary sodium of LMFBR's is a continuing Sodium Technology activity sponsored by the Department of Energy. This paper describes studies directed toward obtaining an understanding of the deposition from sodium of fuel cladding activated corrosion products onto stainless steel alloys and the effect of their diffusion into the base metal on the process required to deco… more

Date: January 1, 1980

Creator: Hill, E. F.; Lutton, J. M. & Maffei, H. P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980

Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical prope… more

Date: June 25, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Material Considerations in the Design of a Bulk Shield for the Fusion Engineering Device

The FED bulk shield provides protection from high-energy neutrons and gamma rays and removes nuclear heat generated. Bulk shield optimization calculations were conducted using the Los Alamos ONEDANT discrete ordinates and the General Atomic PATH point kernel codes. Six candidate steel alloys were considered.

Date: January 1, 1981

Creator: Kirchner, J. & Engholm, B. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Surface damage of molybdenum and TZM alloy under D/sup +/ impact

The surface damage of polycrystalline molybdenum and TZM alloy under 40-, 60-, and 120-keV D/sup +/ impact has been investigated for irradiation in both pulsed and continuous mode for total doses varying from 1.7 x 10/sup 17/ to 2.2 x 10/sup 19/ ions/cm/sup 2/ and for target temperatures verying from ambient temperature to 400/sup 0/C. Analysis by scanning electron microscopy of the MO samples held at ambient temperatures during D/sup +/ irradiations in both pulsed and continuous modes revealed… more

Date: January 1, 1977

Creator: Das, S.K.; Kaminsky, M. & Dusza, P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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CRBRP reactor system shield design and impact of new materials irradiation damage data

Structural materials radiation damage data have received considerable attention in the design of LMFBR permanent reactor structures. A recent FFTF/CRBRP structural materials irradiation experiment, conducted as part of the national program plan for irradiation effects on mechanical properties of LMFBR out-of-core structural materials, has found engineering application in setting energy-dependent neutron exposure limits of irradiated structures. This paper describes the impact of the new irradia… more

Date: January 1, 1980

Creator: Wrights, G.N.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Flow instability in a vertical annulus under steady state and transient conditions

Experimental data have been obtained for the occurrence of flow instability in a vertical annulus under steady state and transient down-flow conditions. The results show that the primary factor affecting the onset of flow instability is the Q{sub ratio} parameter (a measure of the void production in a channel). In addition, it is shown that for steady state conditions good agreement exists between the single annulus data and single tube data based upon the same L/D ratio. The results also indic… more

Date: January 1, 1992

Creator: Fighetti, C.; Kokolis, S.; Maciuca, C.; Reddy, D.G.; Yang, B.; Carrano, V. (Columbia Univ., New York, NY (United States)) et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Liquid metal corrosion considerations in alloy development

Liquid metal corrosion can be an important consideration in developing alloys for fusion and fast breeder reactors and other applications. Because of the many different forms of liquid metal corrosion (dissolution, alloying, carbon transfer, etc.), alloy optimization based on corrosion resistance depends on a number of factors such as the application temperatures, the particular liquid metal, and the level and nature of impurities in the liquid and solid metals. The present paper reviews the va… more

Date: January 1, 1984

Creator: Tortorelli, P. F. & DeVan, J. H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Thermal transport properties of niobium and some niobium base alloys from 80 to 1600/sup 0/K

The electrical resistivities and absolute Seebeck coefficients of 99.8 at. % niobium with a RRR of 36, Nb-4.8 at. % W, Nb-5 at. % Mo, Nb-10 at. % Mo, and Nb-2.4 at. % Mo-2.4 at. % Zr were measured from 80 to 1600/sup 0/K, and the thermal conductivities of the niobium and Nb-5 at. % W were measured from 80 to 1300/sup 0/K. A technique is described for measuring the electrical resistivity and Seebeck coefficient of a specimen during radial heat flow measurements of the thermal conductivity. The t… more

Date: January 1, 1980

Creator: Moore, J. P.; Graves, R. S. & Williams, R. K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Postirradiation cladding strength under biaxial loading with an increasing temperature ramp. [LMFBR]

The flow behavior of unirradiated 20% cold worked AISI 316 tubing during constant pressure, increasing temperature tests was modeled with a constitutive relation approach; strain below approximately 0.2% came predominantly from an anelastic portion of the model while higher strains were predominantly plastic. The flow of cladding sections from irradiated fuel pins was largely restricted to the strain region attributed to anelastic deformation due to reduced ductility compared to unirradiated tu… more

Date: April 1, 1980

Creator: Duncan, D. R. & Hunter, C. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Superplasticity in a nickel silicide alloy: Microstructural and mechanical correlations

The superplastic properties of a nickel silicide based intermetallic alloy have been investigated as a function of strain, strain-rate, and temperature. The evolution of the microstructure during superplasticity, including grain growth, grain refinement, and cavitation, is reviewed. The relationship of the flow stress to strain and to strain-rate and the activation energy of the deformation process have been established. Finally, deformation mechanisms for superplasticity in the alloy at interm… more

Date: January 1, 1991

Creator: Stoner, S.L. (Lawrence Livermore National Lab., CA (United States)); Oliver, W.C. (Oak Ridge National Lab., TN (United States)) & Mukherjee, A.K. (California Univ., Davis, CA (United States). Dept. of Mechanical, Aeronautical and Materials Engineering)

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Effects of nominal and crack-tip strain rate on IGSCC susceptibility in CERT tests

Constant extension rate tests have been performed on sensitized Type 316 stainless steel in oxygenated water (8 ppM O/sub 2/) containing chloride ion impurities (0.5 ppM) over a range of strain rates from 10/sup -5/ to 2 x 10/sup -7/ s/sup -1/. The susceptibility to IGSCC (as quantified by parameters such as crack length at failure) increases with a decrease in strain rate. A model consistent with the observed and postulated crack growth behavior and with a fracture criterion is presented and u… more

Date: September 1, 1983

Creator: Maiya, P.S. & Shack, W.J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Frank loop unfaulting mechanism in fcc metals during neutron irradiation

The unfaulting mechanism whereby sessile Frank dislocation loops evolve into a complex tangle of glissile dislocations during irradiation of face centered cubic metals is not well understood. It is presumed that such loops grow by absorption of point defects until interactions develop which provide sufficient impetus for nucleation of an unfaulting event. The loops then become glissile, interact and form a dislocation network. An alternate mechanism which has been observed to occur in an austen… more

Date: May 1980

Creator: Gelles, D. S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Nuclear performance calculations for the ELMO Bumpy Torus Reactor (EBTR) reference design

The nuclear performance of the ELMO Bumpy Torus Reactor reference design has been calculated using the one-dimensional discrete ordinates code ANISN and the latest available ENDF/B-IV transport cross-section data and nuclear response functions. The calculated results include estimates of the spatial and integral heating rate with emphasis on the recovery of fusion neutron energy in the blanket assembly and minimization of the energy deposition rates in the cryogenic magnet coil assemblies. The … more

Date: December 1, 1977

Creator: Santoro, R. T. & Barnes, J. M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Tritium permeability of structural materials and surface effects on permeation rates

Tritium management in any system always will include containment such that tritium release rates will be less than established limits and also will be as low as practical. The well known properties of hydrogen to permeate through most materials make the complete containment of tritium an impossible task. However, tritium release rates from a given system can be minimized by two primary efforts. First is the selection of a compatible containment material which frequently also will be the structu… more

Date: January 1, 1980

Creator: Bell, J T; Redman, J D & Bittner, H F

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Survey of physical property data for several alloys. [Nitronic 33; copper C10400; copper C17510]

This report summarizes an examination of physical property data available in the literature for six alloys of potential interest to the Toroidal Fusion Core Experiment in the Fusion Energy Program. The properties of thermal expansion, density, specific heat, electrical resistivity, and thermal conductivity were compiled for six alloys: Nitronic 33, a low-nickel, high manganese stainless steel; nickel-base Inconnel Alloys 625, 718, and X-750; and copper alloys C10400 and C17510. The temperatures… more

Date: August 1, 1985

Creator: Pawel, R. E. & Williams, R. K.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Application of ultrasonic waves to assess grain structure in cast stainless steel

Although the ASME code requires the inspection of cast stainless steel (CSS) piping in nuclear reactors, it has not been possible to demonstrate unambiguously that current inspection techniques are adequate. Ultrasonic inspection is difficult because the microstructure of CSS can vary considerably, from elastically isotropic with equiaxed, relatively small grains to elastically anisotropic with a columnar grain structure to a combination of the two. For the near term, improvements that may incr… more

Date: April 1, 1985

Creator: Kupperman, D.S.; Reimann, K.J. & Abrego-Lopez, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Low alloy steels for thick wall pressure vessels. Yearly report, October 1, 1976--September 30, 1977

A summary is presented of progress during the first year of a program to modify current ferrous alloys and develop new low-alloy steels that can be field-fabricated into large-diameter, thick-walled pressure vessels for commercial coal gasifiers. Determination of design criteria for the pressure vessel steels, incorporating information gained through review of the literature and gained through interaction with industry, national laboratory personnel, and research contractors is described. Work … more

Date: January 1, 1977

Creator: Horn, R. M.; Parker, E. R. & Zackay, V. F.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Electrode polarization studies in hot corrosion systems. Progress report, June 1, 1977--May 31, 1978

Analysis of thermodynamic models pertaining to coal gasification is near completion. Model I, comprising a gas phase and a molten salt phase, pertains to laboratory materials testing; Model II incorporates as well a solid carbon phase and is intended to model typical gasifier environments. Anodic and cathodic polarization measurements on iron, 1018 steel, nickel, and 304 and 316 stainless steel have been performed in molten sodium carbonate under air and oxygen; tests under reducing environment… more

Date: February 1, 1978

Creator: Devereux, O.F.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Ultrasonic attenuation as a function of heat treatment and grain size in 79Ni--6Mo--15Fe alloy

A pulse echo ultrasonic technique was used to measure the attenuation coefficient for 79Ni-6Mo-15Fe alloy specimens. The attenuation coefficient was determined using a 25 MHz ultrasonic transducer for specimens which had undergone different time-temperature heat treatments. The ultrasonic attenuation data versus heat treat time was used to assess grain size growth in the specimens.

Date: March 1, 1978

Creator: Gieske, J. H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Practical blanket design for a toroidal fusion reactor

This blanket concept will be examined for use in a tokamak, but the blanket described here is for an Elmo Bumpy Torus Reactor. In this reactor, the plasma region has a diameter of 2.4 meters under the coils, and a diameter of 3.4 meters in the ''bumps'' between coils. For either diameter the segments are divided into twelve buckets in the poloidal plane. There are nine toroidal segments between the center lines of two coils. The blanket is of uniform thickness for all segments, and this dimensi… more

Date: January 1, 1977

Creator: Bettis, E. S.; Barnes, J. M.; Huxford, T. J.; Liu, K. C.; Santoro, R. T. & Watts, H. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Heat exchanger materials for fluidized bed coal combustors

The 4500-h test in the FluiDyne AFBC tells us three things: (1) ferritic and austenitic superheater alloys perform well to approximately 590/sup 0/C (1100/sup 0/F), (2) high-temperature alloys can perform well at approximately 870/sup 0/C (1600/sup 0/F), and (3) they also may fail miserably at approximately 870/sup 0/C (1600/sup 0/F). Additional studies are clearly needed to develop a fundamental understanding of corrosion mechanisms in AFBC and to determine the envelope of safe operating condi… more

Date: January 1, 1980

Creator: Godfrey, T. G.; Copper, R. H.; DeVan, J. H. & Drake, K. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department