SYMPOSIA PAPER Published: 01 January 2004
STP11258S

The Modeling of Radiation-Induced Phosphorus Segregation at Point Defect Sinks in Dilute Fe-P Alloys

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Both the intergranular and intragranular segregation of phosphorus may significantly contribute to irradiation embrittlement of reactor pressure vessel steels. The modeling of phosphorus radiation-induced segregation at cylindrical (dislocations), spherical (precipitates and voids) and flat (sample surfaces, grain boundaries) point defect sinks has been carried out in order to compare the kinetics and extent of segregation at various point defect sinks. Dilute Fe-P alloys relevant to model and VVER-440 pressure vessel steels were considered.

It is shown that the time to reach steady state phosphorus concentration near dislocation or precipitate is much less than that near grain boundary. Although the steady state phosphorus concentration near dislocations or precipitates is much less than that near grain boundary, a “fast” phosphorus segregation at these sinks may lead to decreasing the free phosphorus content in the matrix and to reducing its subsequent accumulation on grain boundaries at high densities of internal sinks. A more significant effect on the kinetics of grain boundary phosphorus segregation could be caused by the contribution of precipitates to point defect sink strength.

Author Information

Stepanov, IA
State Scientific Center of Russian Federation (SSC RF), Institute of Physics and Power Engineering (IPPE), Obninsk, Kaluga region, Russia
Pechenkin, VA
State Scientific Center of Russian Federation (SSC RF), Institute of Physics and Power Engineering (IPPE), Obninsk, Kaluga region, Russia
Konobeev, YV
State Scientific Center of Russian Federation (SSC RF), Institute of Physics and Power Engineering (IPPE), Obninsk, Kaluga region, Russia
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Details
Developed by Committee: E10
Pages: 579–589
DOI: 10.1520/STP11258S
ISBN-EB: 978-0-8031-5494-0
ISBN-13: 978-0-8031-3477-5