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Radiation damage structure in irradiated and annealed 440 WWER-Type reactor pressure vessel steels

Abstract

A review of irradiation damages in WWER-type RPV steels based on conventional Transmission Electron Microscopy investigations in a power reactor and a research reactor, is presented; the samples consist in Cr-Mo-V ferritic steel (15Kh2MFA type). The visible part of radiation-induced defects consists of very fine vanadium carbide precipitates, small dislocation loops and black dots (presumably corresponding) to clusters and particle embryos formed from vacancies and solute-atoms (vanadium, copper, phosphorus) and carbon associated with vanadium. Radiation-induced defects are concentrated at dislocation substructure during irradiation in a power reactor, revealing the role of radiation-enhanced diffusion in damage structure forming process. Contrarily, the distribution of defects resulting from annealing of specimens irradiated in the research reactor is pre-determined by an homogenous distribution of radiation-induced defects prior to annealing. Increasing the number of re-irradiation and annealing cycles, the amount of dislocation loops among all defects seems to be growing. Simultaneously, the dislocation substructure recovers considerably. (authors). 14 refs., 11 figs., 3 tabs.
Authors:
Kocik, J; Keilova, E [1] 
  1. Czech Nuclear Society, Prague (Czech Republic)
Publication Date:
Dec 31, 1993
Product Type:
Conference
Report Number:
NEA-CSNI-R-94-1; CONF-9309237-
Reference Number:
SCA: 360106; 210200; PA: AIX-28:029672; EDB-97:055543; SN: 97001764669
Resource Relation:
Conference: International Atomic Energy Agency (IAEA) specialist meeting on irradiation embrittlement and optimization of annealing, Paris (France), 20-23 Sep 1993; Other Information: PBD: 1993; Related Information: Is Part Of Irradiation embrittlement and optimisation of annealing; PB: 292 p.
Subject:
36 MATERIALS SCIENCE; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; STEEL-CR2MOV; PHYSICAL RADIATION EFFECTS; WWER-3 REACTOR; ANNEALING; DAMAGING NEUTRON FLUENCE; DEFECTS; DISLOCATIONS; IMPURITIES; NEUTRON FLUX; PRESSURE VESSELS; TRANSMISSION ELECTRON MICROSCOPY; WELDED JOINTS
OSTI ID:
455770
Research Organizations:
Nuclear Energy Agency, 75 - Paris (France). Committee on the Safety of Nuclear Installations
Country of Origin:
NEA
Language:
English
Other Identifying Numbers:
Other: ON: DE97620233; TRN: XN9600147029672
Availability:
INIS; OSTI as DE97620233
Submitting Site:
INIS
Size:
pp. 1-11
Announcement Date:

Citation Formats

Kocik, J, and Keilova, E. Radiation damage structure in irradiated and annealed 440 WWER-Type reactor pressure vessel steels. NEA: N. p., 1993. Web.
Kocik, J, & Keilova, E. Radiation damage structure in irradiated and annealed 440 WWER-Type reactor pressure vessel steels. NEA.
Kocik, J, and Keilova, E. 1993. "Radiation damage structure in irradiated and annealed 440 WWER-Type reactor pressure vessel steels." NEA.
@misc{etde_455770,
title = {Radiation damage structure in irradiated and annealed 440 WWER-Type reactor pressure vessel steels}
author = {Kocik, J, and Keilova, E}
abstractNote = {A review of irradiation damages in WWER-type RPV steels based on conventional Transmission Electron Microscopy investigations in a power reactor and a research reactor, is presented; the samples consist in Cr-Mo-V ferritic steel (15Kh2MFA type). The visible part of radiation-induced defects consists of very fine vanadium carbide precipitates, small dislocation loops and black dots (presumably corresponding) to clusters and particle embryos formed from vacancies and solute-atoms (vanadium, copper, phosphorus) and carbon associated with vanadium. Radiation-induced defects are concentrated at dislocation substructure during irradiation in a power reactor, revealing the role of radiation-enhanced diffusion in damage structure forming process. Contrarily, the distribution of defects resulting from annealing of specimens irradiated in the research reactor is pre-determined by an homogenous distribution of radiation-induced defects prior to annealing. Increasing the number of re-irradiation and annealing cycles, the amount of dislocation loops among all defects seems to be growing. Simultaneously, the dislocation substructure recovers considerably. (authors). 14 refs., 11 figs., 3 tabs.}
place = {NEA}
year = {1993}
month = {Dec}
}