Sample records for alloy-tzm

  1. Molybdenum and molybdenum alloys as materials for high temperature furnaces and hot isostatic presses

    Energy Technology Data Exchange (ETDEWEB)

    Aschenbrenner, W.; Palme, R.


    Owing to their excellent high-temperature properties molybdenum and the molybdenum alloy TZM are used as materials for high-temperature furnaces and hot isostatic presses. The setup and the function of the high-temperature furnaces and hot isostatic presses and their applications are described.

  2. Diffusion of Cs into high-temperature alloys

    International Nuclear Information System (INIS)

    Cs concentration profiles have been determined for samples of high temperature alloys (TZM, Nimocast) and single crystals of Mo and Ni, which were kept for 509 hours at 7800C in Cs vapour of 7 x 10-7 torr. As analytical methods scanning Auger electron spectrocopy and secondary ion mass spectrometry combined with Ar ion sputtering have been used. Penetration depths are approximately 100 Angstroem for Mo (110), 300 Angstroem for TZM, 1000 Angstroem for Ni (110) and 1 μm for Nimocast at a concentration level of 0.1 atomic per cent. (orig.)

  3. Thermal analysis and design of a cooling system for a Mach 14 nozzle (United States)

    Mullisen, Ronald; Kaste, Keith


    The analysis and design of a Mach 14 converging diverging nozzle wall liner is provided. The analysis indicates that: no fin on the coolant side of the nozzle wall is optimum, the thermal stresses are dominant, and the critical area is very near the throat. The molybdenum alloy TZM, with a wall thickness of 2.0 mm in the throat area, appears to be the only material capable of meeting design requirements. Additionally, cooling water at 2000 psia with a flow velocity of 25 m/s in the coolant passages is required.

  4. Activation of TZM and stainless steel divertor materials in the NET fusion machine

    International Nuclear Information System (INIS)

    This paper presents the results of the activation and decay heat calculations for the divertor plate materials of the Next European Torus (NET). The basic option assessed enables molybdenum alloy TZM and AISI 316L as material for divertor cooling channels. Burn time, effective irradiation time history, and fluence dependence on activation, decay heat, and contact dose is assessed. Impact of the material impurity level on the radioactive inventory is also investigated. The ANITA code is used, with updated cross sections and decay data libraries based on EFF-2 and EAF-3 evaluation files. The flux-weighted spectrum provided by XSDRNPM or ANISN 1-D codes has been used. The real NET geometry was modelled with the 3-D MCNP Monte Carlo neutron transport code. ((orig.))

  5. Developments toward the use of tungsten as armour material in plasma facing components promoted by Euratom-CEA Association

    International Nuclear Information System (INIS)

    Tungsten is increasingly considered as a prime candidate armour material facing the plasma in fusion experiments (ASDEX, JET, ITER). This material is, however, a challenge for the engineers due to its brittleness at room temperature. Its bonding to structural or cooled substrates is a critical issue. The Euratom-CEA Association promotes the development of evolutionary techniques aiming to produce high performance assemblies between tungsten and various substrates. These are 1) functionally graded tungsten to copper, 2) direct electron beam welding of tungsten to Mo-alloy TZM and 3) the characterisation of tungsten coatings deposited on carbon fibre composite by high energy deposition processes. 1) A functionally graded material eliminates the singular point which weakens the heterogeneous assembly, reducing the stresses and allowing a better behaviour. The sintering of submicronic W-Cu powders is investigated. The green shape is processed from W-CuO powder, which is reduced by a hydrogen flow. The compaction and sintering of layers of various compositions (10 to 30 % Cu) produces an assembly (density of ∼ 94%) with a good cohesion. However, the gradient is not effectively controlled, because of the migration of melt copper during the sintering. Future work aims to improve the process by using spark or microwave assisted sintering. 2) Electron beam welding of Mo-alloy TZM is investigated, to produce high temperature components required by radiation cooled PFCs. They require only mechanical properties and no vacuum sealing. The driving line is to use simple tungsten shapes to reduce the milling cost. In spite of low weldable properties of the refractory alloys, a good bonding up to a depth of 5 mm is obtained. Hardness measurements show that the melt area and the heat affected zone are harder than TZM, the weakest materials at 230 Hv. Quench tests in water from up to 2000oC are done without apparent crack formation. 3) Finally, characterisation techniques are

  6. Thermal and mechanical analysis of the Faraday shield for the Compact Ignition Tokamak

    International Nuclear Information System (INIS)

    The antenna for the ion cyclotron resonance heating (ICRH) system of the Compact Ignition Tokamak (CIT) is protected from the plasma environment by a Faraday shield, an array of gas-cooled metallic tubes. The plasma side of the tubes is armored with graphite tiles, which can be either brazed or mechanically attached to the tube. The Faraday shield has been analyzed using finite element codes to model thermal and mechanical responses to typical CIT heating and disruption loads. Four representative materials (Inconel 718, tantalum-10 tungsten, copper alloy C17510, and molybdenum alloy TZM) and several combinations of tube and armor thicknesses were used in the thermal analysis, which revealed that maximum allowable temperatures were not exceeded for any of the four materials considered. The two-dimensional thermal stress analysis indicated Von Mises stresses greater than twice the yield stress for a tube constructed of Inconel 718 (the original design material) for the brazed-graphite design. Analysis of stresses caused by plasma disruption (/rvec J/ /times/ /rvec B/) loads eliminated the copper and molybdenum alloys as candidate tube materials. Of the four materials considered, tantalum-10 tungsten performed the best for a brazed graphite design, showing acceptable thermal stresses (69% of yield) and disruption stresses (42% of yield). A preliminary thermal analysis of the mechanically attached graphite scheme predicts minimal thermal stresses in the tube. The survivability of the graphite tubes in this scheme is yet to be analyzed. 8 refs., 19 figs., 2 tabs

  7. High-energy high-rate pulsed-power processing of materials by powder consolidation and by railgun deposition. Technical report (Final), 10 April 1985-10 February 1987

    Energy Technology Data Exchange (ETDEWEB)

    Persad, C.; Marcus, H.L.; Weldon, W.F.


    This exploratory research program was initiated to investigate the potential of using pulse power sources for powder consolidation, deposition and other high-energy high-rate processing. The characteristics of the high-energy-high-rate (1MJ/s) powder consolidation using megampere current pulses from a homopolar generator, were defined. Molybdenum Alloy TZM, a nickel-based metallic glass, copper/graphite composites, and P/M aluminum alloy X7091 were investigated. The powder-consolidation process produced high densification rates. Density values of 80% to 99% could be obtained with subsecond high-temperature exposure. Specific energy input and applied pressure were controlling process parameters. Time temperature transformation (TTT) concepts underpin a fundamental understanding of pulsed power processing. Inherent control of energy input, and time-to-peak processing temperature developed to be held to short times. Deposition experiments were conducted using an exploding-foil device (EFD) providing an armature feed to railgun mounted in a vacuum chamber. The material to be deposited - in plasma, gas, liquid, or solid state - was accelerated electromagnetically in the railgun and deposited on a substrate. Deposits of a wide variety of single- and multi-specie materials were produced on several types of substrates. In a series of ancillary experiments, pulsed-skin-effect heating and self quenching of metallic conductors was discovered to be a new means of surface modification by high-energy high-rate-processing.

  8. Chapter 9: The FTU Machine - Design Construction and Assembly

    International Nuclear Information System (INIS)

    The main design features and guidelines for the construction of the 8-T cryogenically cooled Frascati Tokamak Upgrade (FTU) are presented. The main features include the very compact toroidal magnets based on the concept of the 'Bitter' type of coil with wedge-shaped turns, utilized for the first time for the Alcator A and C magnets, and the original configuration of the vacuum vessel (VV) structure, which is fully welded in order to achieve the required high strength and electric resistivity. The present toroidal limiter has been installed following several years of operation, and this installation has required the development of specific remote-handling tools. The toroidal limiter consists of 12 independent sectors made of stainless steel carriers and molybdenum alloy (TZM) tiles. The main fabrication processes developed for the toroidal and poloidal coils as well as for the VV are described. It is to be noted that the assembly procedure has required very accurate machining of all the structures requiring several trials and steps. The machine has shown no problem in operating routinely at its maximum design values (8 T, 1.6 MA)

  9. Results from investigations with an instrumented impact machine on a molybdenum base alloy, nickel base alloys, and Incoloy 800

    International Nuclear Information System (INIS)

    Experiments were performed on the molybdenum base alloy TZM, the nickel base alloys Nimocast 713 LC, Inconel 625, Nimonic 86, Hastelloy S, and the iron base alloy Incoloy 800 with an instrumented impact machine. The results are discussed in terms of absorbed impact energies and dynamic fracture toughness. In all cases the agreement between the energy determined by the dial reading and the energy determined by the integration of the load vs. load point displacement diagram was excellent. A procedure for the determination of the dynamic fracture toughness for load vs. load point displacement diagrams exhibiting high oscillations using an averaged curve is proposed. Using this procedure a pronounced influence of the experiments with tup and chisel (5.0 m/s and 0.1 m/s respectively) on the dynamic fracture toughness is not detectable. Using half the drop height, i.e. halving the total energy, lowers the dynamic fracture toughness values for these types of alloys. Low absorbed impact energies are often combined with high fracture toughness values. In these cases there is no or only a small reserve in deformation and/or stable crack growth. (Auth.)

  10. Neutron irradiation damage of a stress relieved TZM alloy

    International Nuclear Information System (INIS)

    The objective of this work is to study defect microstructures and irradiation hardening in a stress relieved TZM alloy after irradiation in the Fast Flux Test Facility (FFTF) using the Materials Open Test Assembly (MOTA). Disk specimens of the molybdenum alloy TZM that had been stress relieved at 1199 K (929 C) for 0.9 ks (15 min.) were irradiated in the FFTF/MOTA 1F at 679, 793 and 873 K (406, 520, and 600 C) to a fast fluence of ∼9.6 x 1022 n/cm2. Microstructures were observed in a transmission electron microscope (TEM). Dislocation structures consisted of isolated loops, aggregated loops (rafts) and elongated dislocations. The size of the loops increased with the irradiation temperature. Void swelling was about 1 and 2% at 793 and 873 K (520 and 600 C), respectively. A void lattice was developed in the body centered cubic (bcc) structure with a spacing of 26 - 28 nm. The fine grain size (0.5 - 2 μm) was retained following high temperature irradiation, indicating that the stress relief heat treatment may extend the material's resistance to radiation damage up to high fluence levels. Microhardness measurements indicated that irradiation hardening increased with irradiation temperature. The relationship between the microstructure and the observed hardening was determined

  11. Parametric study of FER first wall and divertor plate performance

    International Nuclear Information System (INIS)

    Thermal, mechanical, and lifetime performance of various first wall and divertor plate materials were examined over a broad range of conditions, representative of those considered for next-generation tokamaks such as FER. Candidate plasma side materials include beryllium, graphite, silicon carbide, molybdenum, tantalum, and tungsten. Copper, copper alloy C17510, austenitic stainless steel (316SS), ferritic stainless steel (HT-9), vanadium alloy V-15Cr-5Ti, and molybdenum alloy TZM were considered as candidate heat sink/structural materials. Performance was examined at heat fluxes ranging from 0.05 MW/m2 for the first wall up to 5.0 MW/m2 for the divertor plate. Ion flux, plasma edge temperature, burn time per pulse, and number of operating cycles were the other major parameters varied in this study. The analysis model used for these studies includes: (1) a thermal model; (2) a thermal stress model; (3) a disruption erosion model; (4) a sputtering erosion model; and (5) a fatique lifetime model. Results show that recommended first wall and divertor plate designs perform adequately over most of the range of conditions considered for FER design options. Thermal shock of the plasma facing material during intense disruption heating and radiation damage and temperature limitations for graphite are identified as major concerns reguiring experimental investigation. (author)

  12. Mechanical properties of TZM and of different grades of massive molybdenum

    International Nuclear Information System (INIS)

    With regard to the possible use of the molybdenum base alloy TZM (Mo-0,5Ti-0,8Zr) as construction material, a series of mechanical tests were carried out such as creep tests at 8500C, fatigue tests at room temperature and 8500C as well as fracture toughness tests. Different charges were available (L-TZM and S-TZM with different amounts of deformation). There were also considerations on welded joints (electron-beam welded and TIG welded). The fracture deformation capacity at room temperature is insufficient for all welded joints. The fracture toughness values resulting from the quasistatic test, are low (KIC ≅ 13-18 MPa.m1/2), whereas values from instrumented notched-bar impact tests at an impact speed of 5 m/s can reach (KQd ≅ 56 MPa.m1/2). The fatigue strengths of the electron-beam welded specimens are clearly below those of the base material. Moreover, the influence of the carbon content on the material properties is discussed. (orig./MM)

  13. Sulfidation-resistant alloy for coal gasification service. Quarterly report, September 1--November 30, 1977

    International Nuclear Information System (INIS)

    An Fe-18Cr-5Al-1Mo-1Hf alloy has been tested in synthetic coal gasification atmospheres at 500 and 1000 psi pressure. Resistance to attack is similar to that observed at atmospheric pressure. Tests also have been made at high pressure in a low P/sub O2/-high P/sub S2/ atmosphere representative of low Btu gasification. The alloy did not resist attack under these conditions and has a transition to non-protective behavior with decreasing P/sub O2/ and/or increasing P/sub S2/. A molybdenum alloy (TZM-Mo) is being screened for sulfidation resistance in coal gasification atmospheres. Initial tests at 18000F in the DOE/MPC gas mixture show a parabolic rate behavior with negligible attack. Extrapolation of the data indicates a potential loss of 0.2 mil in one year, with 1% H2S in the gas. Samples will be exposed to a cumulative time of 4000 hr to obtain more accurate rate data. Impact tests indicate that Al and Si lower the notched impact toughness and raise the ductile to brittle transition temperature of Fe-Cr alloys with 17-19Cr. The addition of 1 to 2% Mo slightly improves impact behavior. An Fe-18Cr-5Al-1Mo-1Hf alloy is concluded to have the best combination of corrosion resistance and mechanical properties. This composition and an upper limit composition of 19Cr-6Al-2Mo-1Hf have been selected for the final Phase III evaluation. Two 50-lb ingots of each composition have been vacuum induction melted and cast successfully