Determination of the threshold values for corrosion fatigue crack growth rate of pressure vessel steels in PWR primary water

Hannu Hänninen, Esko Arilahti, Ulla Ehrnsten

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

Original languageEnglish
Title of host publication Proceedings of the 5th International Symposium on Environments Degradation of Materials in Nuclear Power System - Water Reactors
EditorsP. Geoffrey
PublisherAmerican Nuclear Society ANS
Pages545-553
ISBN (Print) 978-0-89448-173-4
Publication statusPublished - 1992
MoE publication typeB3 Non-refereed article in conference proceedings
Event5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors - Monterey, United States
Duration: 25 Aug 199129 Aug 1991

Conference

Conference5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors
CountryUnited States
CityMonterey
Period25/08/9129/08/91

Cite this

Hänninen, H., Arilahti, E., & Ehrnsten, U. (1992). Determination of the threshold values for corrosion fatigue crack growth rate of pressure vessel steels in PWR primary water. In P. Geoffrey (Ed.), Proceedings of the 5th International Symposium on Environments Degradation of Materials in Nuclear Power System - Water Reactors (pp. 545-553). American Nuclear Society ANS.
Hänninen, Hannu ; Arilahti, Esko ; Ehrnsten, Ulla. / Determination of the threshold values for corrosion fatigue crack growth rate of pressure vessel steels in PWR primary water. Proceedings of the 5th International Symposium on Environments Degradation of Materials in Nuclear Power System - Water Reactors. editor / P. Geoffrey. American Nuclear Society ANS, 1992. pp. 545-553
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Hänninen, H, Arilahti, E & Ehrnsten, U 1992, Determination of the threshold values for corrosion fatigue crack growth rate of pressure vessel steels in PWR primary water. in P Geoffrey (ed.), Proceedings of the 5th International Symposium on Environments Degradation of Materials in Nuclear Power System - Water Reactors. American Nuclear Society ANS, pp. 545-553, 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors, Monterey, United States, 25/08/91.

Determination of the threshold values for corrosion fatigue crack growth rate of pressure vessel steels in PWR primary water. / Hänninen, Hannu; Arilahti, Esko; Ehrnsten, Ulla.

Proceedings of the 5th International Symposium on Environments Degradation of Materials in Nuclear Power System - Water Reactors. ed. / P. Geoffrey. American Nuclear Society ANS, 1992. p. 545-553.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

TY - GEN

T1 - Determination of the threshold values for corrosion fatigue crack growth rate of pressure vessel steels in PWR primary water

AU - Hänninen, Hannu

AU - Arilahti, Esko

AU - Ehrnsten, Ulla

PY - 1992

Y1 - 1992

UR - http://www.ans.org/store/item-700176/

M3 - Conference article in proceedings

SN - 978-0-89448-173-4

SP - 545

EP - 553

BT - Proceedings of the 5th International Symposium on Environments Degradation of Materials in Nuclear Power System - Water Reactors

A2 - Geoffrey, P.

PB - American Nuclear Society ANS

ER -

Hänninen H, Arilahti E, Ehrnsten U. Determination of the threshold values for corrosion fatigue crack growth rate of pressure vessel steels in PWR primary water. In Geoffrey P, editor, Proceedings of the 5th International Symposium on Environments Degradation of Materials in Nuclear Power System - Water Reactors. American Nuclear Society ANS. 1992. p. 545-553