About: SCC Investigation of Pre-Irradiated Core Shroud Weld HAZ Specimens under Simulated BWR Environmental Conditions in a Research Reactor

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About: SCC Investigation of Pre-Irradiated Core Shroud Weld HAZ Specimens under Simulated BWR Environmental Conditions in a Research Reactor Goto Sponge NotDistinct Permalink

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rdf:type	skos:Concept http://linked.opendata.cz/ontology/domain/vavai/Vysledek
Description	This paper presents final results of a project aiming to produce reliable crack growth data on the Nbstabilized austenitic stainless steel 1.4550 (A347) under the simultaneous influence of BWR-coolant and neutron/gamma irradiation.Crack growth rates of HAZ materials pre-irradiated to 6.0x1020 and 1.5x1021 n/cm2 (E > 1 MeV), i.e. 0.9 and 2.3 dpa, were 2 to 8 times higher than the corresponding non-irradiated base material values under constant load. The HAZ CGR data were very similar to the CGR data of 1.4550 (A347) base metal irradiated to an equivalent fluence level. The experimental data are evaluated and presented together with fractographical and metallographical investigations. This paper presents final results of a project aiming to produce reliable crack growth data on the Nbstabilized austenitic stainless steel 1.4550 (A347) under the simultaneous influence of BWR-coolant and neutron/gamma irradiation.Crack growth rates of HAZ materials pre-irradiated to 6.0x1020 and 1.5x1021 n/cm2 (E > 1 MeV), i.e. 0.9 and 2.3 dpa, were 2 to 8 times higher than the corresponding non-irradiated base material values under constant load. The HAZ CGR data were very similar to the CGR data of 1.4550 (A347) base metal irradiated to an equivalent fluence level. The experimental data are evaluated and presented together with fractographical and metallographical investigations. (en)
Title	SCC Investigation of Pre-Irradiated Core Shroud Weld HAZ Specimens under Simulated BWR Environmental Conditions in a Research Reactor SCC Investigation of Pre-Irradiated Core Shroud Weld HAZ Specimens under Simulated BWR Environmental Conditions in a Research Reactor (en)
skos:prefLabel	SCC Investigation of Pre-Irradiated Core Shroud Weld HAZ Specimens under Simulated BWR Environmental Conditions in a Research Reactor SCC Investigation of Pre-Irradiated Core Shroud Weld HAZ Specimens under Simulated BWR Environmental Conditions in a Research Reactor (en)
skos:notation	RIV/46356088:_____/09:#0001197!RIV13-MPO-46356088
http://linked.open...avai/riv/aktivita	N
http://linked.open...avai/riv/aktivity	N
http://linked.open...vai/riv/dodaniDat	2013
http://linked.open...aciTvurceVysledku	Všolák, Rudolf Kysela, Jan Hojná, Anna Ernestová, Miroslava
http://linked.open.../riv/druhVysledku	D - Článek ve sborníku
http://linked.open...iv/duvernostUdaju	S - Úplné a pravdivé údaje nepodléhající ochraně podle zvláštních právních předpisů
http://linked.open...titaPredkladatele	ÚJV Řež, a. s.
http://linked.open...dnocenehoVysledku	340322
http://linked.open...ai/riv/idVysledku	RIV/46356088:_____/09:#0001197
http://linked.open...riv/jazykVysledku	eng - angličtina
http://linked.open.../riv/klicovaSlova	SCC; crack growth rate; corrosion fatigue (en)
http://linked.open.../riv/klicoveSlovo	crack growth rate SCC corrosion fatigue
http://linked.open...ontrolniKodProRIV	[C6C9F337736F]
http://linked.open...v/mistoKonaniAkce	Virginia Beach, VA., USA
http://linked.open...i/riv/mistoVydani	La Grange Park, Illinois 60526, USA
http://linked.open...i/riv/nazevZdroje	Proceedings of the 14th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
http://linked.open...in/vavai/riv/obor	JF
http://linked.open...ichTvurcuVysledku	4 (xsd:int)
http://linked.open...cetTvurcuVysledku	9 (xsd:int)
http://linked.open...UplatneniVysledku	2009
http://linked.open...iv/tvurceVysledku	Kysela, Jan Všolák, Rudolf Hojná, Anna Ernestová, Miroslava
http://linked.open...vavai/riv/typAkce	WRD - Světová
http://linked.open.../riv/zahajeniAkce	2009-01-01 (xsd:date)
number of pages	12 (xsd:int)
http://purl.org/ne...btex#hasPublisher	ANS
https://schema.org/isbn	978-0-89448-070-6

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