Detail publikace
TEM Analysis of Irradiation Effects in Reactor Core Internals
Michalička J. Keilová E. Kočík J.
Český název
TEM Analysis of Irradiation Effects in Reactor Core Internals
Anglický název
TEM Analysis of Irradiation Effects in Reactor Core Internals
Typ
článek ve sborníku ve WoS nebo Scopus
Jazyk
cs
Originální abstrakt
This paper surveys new results regarding microstructural development of irradiated material from VVER 440 reactors core internals of NPP Greiswald decommissioned after 15 years in service. The presented study is a part of project aimed to evaluation of structure-mechanical properties and to lifetime reassessment of the NPPs reactor core internals. Obtained doses were 2.4, 5.2 and 11.4 dpa and irradiation temperatures lied from 270 to 400C. For a comparison with irradiated stage, non-irradiated segments were cut from the same location as the active segments, but from another NPPs reactor which had never been in service.
Český abstrakt
This paper surveys new results regarding microstructural development of irradiated material from VVER 440 reactors core internals of NPP Greiswald decommissioned after 15 years in service. The presented study is a part of project aimed to evaluation of structure-mechanical properties and to lifetime reassessment of the NPPs reactor core internals. Obtained doses were 2.4, 5.2 and 11.4 dpa and irradiation temperatures lied from 270 to 400C. For a comparison with irradiated stage, non-irradiated segments were cut from the same location as the active segments, but from another NPPs reactor which had never been in service.
Anglický abstrakt
This paper surveys new results regarding microstructural development of irradiated material from VVER 440 reactors core internals of NPP Greiswald decommissioned after 15 years in service. The presented study is a part of project aimed to evaluation of structure-mechanical properties and to lifetime reassessment of the NPPs reactor core internals. Obtained doses were 2.4, 5.2 and 11.4 dpa and irradiation temperatures lied from 270 to 400C. For a comparison with irradiated stage, non-irradiated segments were cut from the same location as the active segments, but from another NPPs reactor which had never been in service.
Klíčová slova česky
TEM, Radiation Induced Defects, Swelling, Reactor Core Internals
Klíčová slova anglicky
TEM, Radiation Induced Defects, Swelling, Reactor Core Internals
Vydáno
13.07.2009
ISSN
1335-0803
Kniha
Materials Engineering
Ročník
16
Číslo
3a/2009
Strany od–do
163–168
Počet stran
6
BIBTEX
@inproceedings{BUT95256,
author="Jan {Michalička} and Eliška {Keilová} and Jan {Kočík},
title="TEM Analysis of Irradiation Effects in Reactor Core Internals",
booktitle="Materials Engineering",
year="2009",
volume="16",
number="3a/2009",
month="July",
pages="163--168",
issn="1335-0803"
}