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

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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

Book details:

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 LibraryOL17964648M

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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.