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3 edition of The effects of Fe-Ni-Co-V structural alloys on fusion reactor neutronic performance found in the catalog.

The effects of Fe-Ni-Co-V structural alloys on fusion reactor neutronic performance

Oak Ridge National Laboratory. Engineering Physics Division.

The effects of Fe-Ni-Co-V structural alloys on fusion reactor neutronic performance

by Oak Ridge National Laboratory. Engineering Physics Division.

  • 56 Want to read
  • 15 Currently reading

Published by Dept. of Energy, Oak Ridge National Laboratory, for sale by the National Technical Information Service] in Oak Ridge, Tenn, [Springfield, Va .
Written in English

    Subjects:
  • Fusion reactors -- Design and construction,
  • Building materials, Effect of radiation on,
  • Alloys, Effect of radiation on

  • Edition Notes

    StatementJ. M. Barnes ... [et al.], Computer Sciences Division
    SeriesORNL/TM ; 6543
    ContributionsBarnes, J. M. 1943-, Union Carbide Corporation. Computer Sciences Division
    The Physical Object
    Paginationiii, 11 p. ;
    Number of Pages11
    ID Numbers
    Open LibraryOL14881678M

    complex Fe–Cr base alloys provide the basis for assessing the underlying radiation performance processes even in complex alloy systems. The new level of understanding on the irradia-tion performance of this alloy system will also facilitate the development of modeling capabilities to better predict future alloy performance and development.   The effect of Al content on the mechanical properties of Fe–Al–Mn–C alloys is shown in figure figure6 6 [13, 17, 25, 33]. All the alloys were solution-treated at temperatures above °C before water quenching. Tensile tests were carried out at strain rates from × 10 −4 to 1 × 10 −3 s −1 at room temperature.

    @article{osti_, title = {Understanding phase stability of Al-Co-Cr-Fe-Ni high entropy alloys}, author = {Zhang, Chuan and Zhang, Fan and Diao, Haoyan and Gao, Michael C. and Tang, Zhi and Poplawsky, Jonathan D. and Liaw, Peter K.}, abstractNote = {The concept of high entropy alloy (HEA) opens a vast unexplored composition range for alloy design. 3-forming alloys is the formation of volatile Cr species due to chromium evaporation, which will migrate to and thus poison the cathode, resulting in SOFC performance degradation Two approaches can be taken to address this issue: 9Surface coating approach 9Alloy design approach Cr-free or low Cr Fe-Ni-Co alloys tailored for SOFC interconnect.

    Ni alloys to achieve a compact and protective chromia scale. A series of Ni-xCr model alloys were made and used for these tests. The second was to examine the effect of surface finish on the oxidation behavior of Grade 91 ferritic-martensitic steel. The low-temperature, Fe-rich portion of the Fe-Ni-S phase diagram was determined from Fe-Ni-S alloys (,5,10,20, and 30 wt.% Ni, 10 wt % S, balance Fe) heat treated at °C intervals from to °C. The microstructure and microchemistry of the phases in the heat treated Fe-Ni-S alloys were studied using a high-resolution field-emission gun (FEG) scanning electron microscope (SEM.


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The effects of Fe-Ni-Co-V structural alloys on fusion reactor neutronic performance by Oak Ridge National Laboratory. Engineering Physics Division. Download PDF EPUB FB2

The effects of Fe-Ni-Co-V structural alloys on fusion reactor neutronic performance. [J M Barnes; Oak Ridge National Laboratory. Engineering Physics Division. Abstract. The temperature dependence of the transport properties [thermal conductivity (λ), electrical resistivity (ρ), and thermopower (S)] and the thermal expansion coefficients [differential (α o) and mean α m)] were determined in the range to K for three alloys: water quenched V(Fe 0.

22 Co ) 3, ordered V(Fe Co ) 3 and ordered V(Fe Ni ) 3, modified with by: 1. For in-core nuclear applications of Ni alloys, it is extremely important to take into account the neutron spectrum, especially when considering radiation effects for reactor core components at the periphery of the core where the thermal neutron flux tends to be higher than the fast neutron flux in all : Malcolm Griffiths.

In order to evaluate the suitability of the titanium alloys as structural materials for a fusion reactor, we have considered first the problems coming from neutron-induced radioactivity, and then we have characterized a Ti-6Al4V alloy from the mechanical point of view, in different conditions (temperature, strain rate, morphology).

Size: 1MB. In this article, the more details of alloying effects on both structural and magnetic properties of Fe 50 Co 30 Ni 20 system have been investigated.

In comparison to the previous researches, the effect of the specific amount of iron, cobalt and nickel and also heat treatment of the alloy were studied which have been less considered. by: Study on the effect of neutron irradiation (fluence up to 32 dpa) on the tensile properties of XHM-1 alloy has shown that the ultimate tensile strength, yield strength and, especially, total elongation δ tot and uniform elongation δ u at irradiation temperatures up to °C and subsequent testing temperatures up to °C vary to a little extent.

Hence, low temperature radiation embrittlement does not occur in the alloy. Performance of the Fe-Ni-Cr steel alloy in high temperature molten liquid lead Article (PDF Available) in Journal of Physics Conference Series March with 38 Reads.

@article{osti_, title = {Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys}, author = {Field, Kevin G. and Briggs, Samuel A. and Sridharan, Kumar and Howard, Richard H. and Yamamoto, Yukinori}, abstractNote = {The development and understanding of the mechanical properties of neutron-irradiated FeCrAl alloys is increasingly a critical need as these alloys.

The weight loss measurements revealed that alloys with a high Ni and a low Fe content offer a higher corrosion resistance in this gas atmosphere, than alloys with a low Ni and high Fe content.

Structural materials in nuclear energy systems are exposed to a variety of operating conditions that can produce significant degradation in material properties. This chapter provides an overview of the degradation processes in structural alloys associated with elevated temperatures, applied mechanical stress, and neutron irradiation.

Abstract. This paper is concerned with the effect of ternary additions of Ni on the decomposition of austenite in Fe-Cu alloys. It is shown that the transformation kinetics, transformation structures and associated precipitate morphologies are sensitive functions of the Ni content.

Areas in need of inves- tigation are numerous, but the more important areas of uncertainty which exist at this time for vanadium alloys are as follows: (1) effects of cyclic loading on general mechanical properties; (2) fatigue and FCG data at fusion reactor gas and damage levels; (3) effect of helium and hydrogen and displacement damage on microstructural stability; (4) poor database for the effects of.

From a safety point of view, it is important to study the damages and reliability of molten salt reactor structural alloy materials, which are subjected to extreme environments due to neutron. and breeding blanket structural materials for future fusion reactors.

Their use for these applications requires a careful assessment of their mechanical stability under high energy neutron irradiation. In this work, the characterization of Fe-Cr model alloys with different Cr content with respect to. Low-expansion alloys have been joined to Al2O3producing nearly stress-free joints.

This work investigates the use of powder metallurgy to tailor the coefficient of thermal expansion of Fe-Ni-Co.

Structure of Fe–Ni and Fe–Ni–S molten alloys by neutron diffraction. AbstractThis paper overviews the effects of some precipitates in Fe–Ni base boilers materials. The volume fraction of these precipitates is usually below 10% for maintaining the microstructure stability and manufacture ability.

They appear in a number of morphologies, but all of them improve the creep strength when they exist in small size. In addition, in a fusion reactor, high energy neutrons will produce Ni, Zn and smaller amount of Cobalt in copper and copper alloys, producing a significant decrease of the electrical and thermal.

[10] The fourth experiment was carried out at the relatively low pressures of – GPa and – K using 60 μm‐culet anvils. This run aimed to reproduce the earlier experimental results by Dubrovinsky et al., who reported the phase transition from hcp to bcc structure in Fe Ni above GPa and K.

More recent experimental study by Sakai et al. found that hcp Fe Micro-mechanics of irradiated Fe-Cr alloys for fusion reactors Abstract: In the absence of a fusion neutron source, research on the structural integrity of materials in the fusion environment relies on current fission data and simulation methods.

Abstract. Fe-Ni-=B alloy particles have been prepared by reducing transition metal ions in an aqueous solution by addition of an aqueous solution of NaBH amount of amorphous and crystalline phases is shown to depend on the NaBH 4 molarity and the pH in the salt solution.

Amorphous alloy particles with the boron content ranging between 9 and 19 at. Fe–Ni alloy nanoparticles with various alloy components were fabricated by a direct current arc-discharge method. By dispersing the nanoparticles homogeneously into a paraffin matrix, the complex permittivity (εr=εr′+iεr″) and permeability (μr=μr′+iμr″) of the nanoparticles have been investigated in the frequency range of 2–18 GHz and the effects of alloy components on the.FeCrAl alloys are a class of alloys that have seen increased interest for nuclear power applications including as accident tolerant fuel cladding, structural components for fast fission reactors, and as first wall and blanket structures for fusion reactors.

FeCrAl alloys are under consideration for these applications due to their inherent corrosion resistance, stress corrosion cracking resistance.