Change in the Properties of Structural Materials Under Irradiation: Role of Radiation-Induced Segregation

There are several alternative strategies for the development of nuclear power [1, 2]. One of the basic requirements imposed on the future nuclear power technology is its large scale, which presupposes a higher level of safety for all its elements ranging from reactor facilities to NFC technologies [...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2014-09, Vol.116 (5), p.301-310
Main Authors: Pechenkin, V. A., Chernova, A. D., Molodtsov, V. L., Lysova, G. V., Konobeev, Yu. V.
Format: Article
Language:English
Subjects:
60th ANNIVERSARY OF THE STARTUP OF THE WORLD’S FIRST NUCLEAR POWER PLANT IN OBNINSK
Alloys
Analysis
Building materials
Chemical elements
Chromium alloys
Development strategies
Grain boundaries
Hadrons
Heavy Ions
Irradiation
Lead
Metals
Nuclear Chemistry
Nuclear Energy
Nuclear Physics
Nuclear power plants
Nuclear reactors
Physics
Physics and Astronomy
Point defects
Radiation
Reactors
Sinkholes
Studies
Systems design
Temperature
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Summary:There are several alternative strategies for the development of nuclear power [1, 2]. One of the basic requirements imposed on the future nuclear power technology is its large scale, which presupposes a higher level of safety for all its elements ranging from reactor facilities to NFC technologies [3, 4]. One direction for organizing a new technological platform for nuclear power, work on which is now being performed at the State Corporation Rosatom, is the development of innovative fast reactors which have extreme temperatures and dose loads and are cooled by sodium, lead and lead-bismuth [5, 6]. In this connection, research on the properties of structural materials under irradiation has not lost its urgency. Metals and alloys irradiated by damaging particles become supersaturated with point defects and radiation-accelerated diffusion. As a result of radiation-induced segregation, the composition of the alloys becomes nonuniform near sinks for point defects (the boundaries of the samples and grains, dislocations, loops, pores and segregations). This is caused by two mechanisms: 1) the presence of a concentration gradient of point defects near sinks and the difference of the diffusion mobility of the components of an alloy and 2) the formation of complexes of certain chemical elements of the alloy with point defects and flows of point defects toward sinks.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-014-9857-5