European Project "Supercritical Water Reactor

Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests

Radek Novotny, Premysl Janík, Aki Toivonen, Anna Ruiz, Zoltan Szaraz, Jan Siegl, Petr Hausild, Sami Penttilä

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

Abstract

The main target of the HPLWR Phase 2 follow-up FP7 project “Fuel Qualification Test for Super Critical Water Reactor” is to make significant progress towards the design, analysis and licensing of a fuel assembly cooled with supercritical water in a research reactor which also includes the material research on those in-core materials which could be licensed in near future. In frame of WP4 - Pre-qualification, stress corrosion cracking (SCC) resistance of three selected austenitic stainless steels 08Cr18Ni10Ti (equivalent of AISI 321), AISI 347H and AISI 316L was investigated by conducting slow strain rate tensile tests in an autoclave in 550°C supercritical water. SCC susceptibility was evaluated using three criteria: loss of mechanical properties compared to those in inert environment, fractographic analysis of the fracture surfaces and finally analysis of secondary cracks. Obtained results were compared to those available in the literature and utilization of these results is discussed. Based on the results of SSRT tests and following fractographic analysis, 316L was selected as the best performer.
Original languageEnglish
Title of host publication Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015)
PublisherVTT Technical Research Centre of Finland
Number of pages15
EditionUSB stick
ISBN (Electronic)978-951-38-8289-1
ISBN (Print)978-951-38-8290-7
Publication statusPublished - 2015
MoE publication typeB3 Non-refereed article in conference proceedings
Event7th International Symposium on Supercritical Water-Cooled Reactors, ISSCWR-7 - Helsinki, Finland
Duration: 15 Mar 201518 Mar 2015

Publication series

NameVTT Technology
PublisherVTT
Number216
ISSN (Electronic)2242-1211

Conference

Conference7th International Symposium on Supercritical Water-Cooled Reactors, ISSCWR-7
Abbreviated titleISSCWR-7
CountryFinland
CityHelsinki
Period15/03/1518/03/15

Fingerprint

Stress corrosion cracking
Water
Research reactors
Autoclaves
Austenitic stainless steel
Strain rate
Cracks
Mechanical properties

Cite this

Novotny, R., Janík, P., Toivonen, A., Ruiz, A., Szaraz, Z., Siegl, J., ... Penttilä, S. (2015). European Project "Supercritical Water Reactor: Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests. In Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015) (USB stick ed.). [2078] VTT Technical Research Centre of Finland. VTT Technology, No. 216
Novotny, Radek ; Janík, Premysl ; Toivonen, Aki ; Ruiz, Anna ; Szaraz, Zoltan ; Siegl, Jan ; Hausild, Petr ; Penttilä, Sami. / European Project "Supercritical Water Reactor : Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests. Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015). USB stick. ed. VTT Technical Research Centre of Finland, 2015. (VTT Technology; No. 216).
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abstract = "The main target of the HPLWR Phase 2 follow-up FP7 project “Fuel Qualification Test for Super Critical Water Reactor” is to make significant progress towards the design, analysis and licensing of a fuel assembly cooled with supercritical water in a research reactor which also includes the material research on those in-core materials which could be licensed in near future. In frame of WP4 - Pre-qualification, stress corrosion cracking (SCC) resistance of three selected austenitic stainless steels 08Cr18Ni10Ti (equivalent of AISI 321), AISI 347H and AISI 316L was investigated by conducting slow strain rate tensile tests in an autoclave in 550°C supercritical water. SCC susceptibility was evaluated using three criteria: loss of mechanical properties compared to those in inert environment, fractographic analysis of the fracture surfaces and finally analysis of secondary cracks. Obtained results were compared to those available in the literature and utilization of these results is discussed. Based on the results of SSRT tests and following fractographic analysis, 316L was selected as the best performer.",
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Novotny, R, Janík, P, Toivonen, A, Ruiz, A, Szaraz, Z, Siegl, J, Hausild, P & Penttilä, S 2015, European Project "Supercritical Water Reactor: Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests. in Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015). USB stick edn, 2078, VTT Technical Research Centre of Finland, VTT Technology, no. 216, 7th International Symposium on Supercritical Water-Cooled Reactors, ISSCWR-7, Helsinki, Finland, 15/03/15.

European Project "Supercritical Water Reactor : Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests. / Novotny, Radek; Janík, Premysl; Toivonen, Aki; Ruiz, Anna; Szaraz, Zoltan; Siegl, Jan; Hausild, Petr; Penttilä, Sami.

Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015). USB stick. ed. VTT Technical Research Centre of Finland, 2015. 2078 (VTT Technology; No. 216).

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

TY - GEN

T1 - European Project "Supercritical Water Reactor

T2 - Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests

AU - Novotny, Radek

AU - Janík, Premysl

AU - Toivonen, Aki

AU - Ruiz, Anna

AU - Szaraz, Zoltan

AU - Siegl, Jan

AU - Hausild, Petr

AU - Penttilä, Sami

PY - 2015

Y1 - 2015

N2 - The main target of the HPLWR Phase 2 follow-up FP7 project “Fuel Qualification Test for Super Critical Water Reactor” is to make significant progress towards the design, analysis and licensing of a fuel assembly cooled with supercritical water in a research reactor which also includes the material research on those in-core materials which could be licensed in near future. In frame of WP4 - Pre-qualification, stress corrosion cracking (SCC) resistance of three selected austenitic stainless steels 08Cr18Ni10Ti (equivalent of AISI 321), AISI 347H and AISI 316L was investigated by conducting slow strain rate tensile tests in an autoclave in 550°C supercritical water. SCC susceptibility was evaluated using three criteria: loss of mechanical properties compared to those in inert environment, fractographic analysis of the fracture surfaces and finally analysis of secondary cracks. Obtained results were compared to those available in the literature and utilization of these results is discussed. Based on the results of SSRT tests and following fractographic analysis, 316L was selected as the best performer.

AB - The main target of the HPLWR Phase 2 follow-up FP7 project “Fuel Qualification Test for Super Critical Water Reactor” is to make significant progress towards the design, analysis and licensing of a fuel assembly cooled with supercritical water in a research reactor which also includes the material research on those in-core materials which could be licensed in near future. In frame of WP4 - Pre-qualification, stress corrosion cracking (SCC) resistance of three selected austenitic stainless steels 08Cr18Ni10Ti (equivalent of AISI 321), AISI 347H and AISI 316L was investigated by conducting slow strain rate tensile tests in an autoclave in 550°C supercritical water. SCC susceptibility was evaluated using three criteria: loss of mechanical properties compared to those in inert environment, fractographic analysis of the fracture surfaces and finally analysis of secondary cracks. Obtained results were compared to those available in the literature and utilization of these results is discussed. Based on the results of SSRT tests and following fractographic analysis, 316L was selected as the best performer.

M3 - Conference article in proceedings

SN - 978-951-38-8290-7

T3 - VTT Technology

BT - Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015)

PB - VTT Technical Research Centre of Finland

ER -

Novotny R, Janík P, Toivonen A, Ruiz A, Szaraz Z, Siegl J et al. European Project "Supercritical Water Reactor: Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests. In Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015). USB stick ed. VTT Technical Research Centre of Finland. 2015. 2078. (VTT Technology; No. 216).