The main target of the EUROATOM FP7 project “Fuel Qualification Test for SCWR” is to make significant progress toward the design, analysis, and licensing of a fuel assembly cooled with supercritical water in a research reactor. The program of dedicated Work Package (WP4)-Prequalification was focused on evaluation of general corrosion resistance of three preselected austenitic stainless steels, 08Cr18Ni10Ti, AISI 347H, and AISI 316L, which should be prequalified for application as a cladding material for fuel qualification tests in supercritical water. Therefore, the experiments in support of WP4 concentrated on 2000-hr corrosion exposures in 25-MPa supercritical water (SCW) at two different temperatures 550°C and 500°C dosed with both 150 and 2000 ppb of dissolved oxygen content. Moreover, the water chemistry effect was investigated by conducting tests in 550°C SCW with 1.5 ppm of dissolved hydrogen content. At first, corrosion coupons were exposed for 600, 1400, and 2000 hrs in Joint Research Centre-Institute for Energy and Transport (JRC-IET), VTT Technical Research Centre of Finland Ltd. (VTT), and Shanghai Jiao Tong University (SJTU) autoclaves connected to the recirculation loop, allowing continual water chemistry control during the test. The following examination of exposed specimens consisted of weight-change calculations and detailed macro- and microscopic investigation of oxide layers using scanning electron microscope (SEM) and energy-dispersive X-ray spectroscopy (EDX). With respect to general corrosion results, all tested steels showed sufficient corrosion resistance in SCW conditions taking into account the conditions foreseen for future fuel qualification test in the research reactor in CVR Rez. When the results of weight-change calculations were compared for all three materials, it was found that the corrosion resistance increased in the following order: . Results obtained in hydrogen water chemistry (HWC) did not indicate any significant beneficial effect compared to tests in SCW with 150 or 2000 ppb dissolved oxygen content. Additional tests were dedicated to investigation of the surface-finish effect. In these exposures, polished, sand-blasted, and plane-milled surface-finish techniques were investigated. The beneficial effect of surface cold work in particular of sand-blasting was clearly demonstrated.
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e-mail: Radek.Novotny@ec.europa.eu
e-mail: janikpremek@gmail.com
e-mail: Aki.Toivonen@vtt.fi
e-mail: Anna.Ruiz@ec.europa.eu
e-mail: Zoltan.Szaraz@ec.europa.eu
e-mail: lfzhang@sjtu.edu.cn
e-mail: Jan.Siegl@fjfi.cvut.cz
e-mail: Petr.Hausild@fjfi.cvut.cz
e-mail: Sami.Penttilä@vtt.fi
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July 2016
Research Papers
European Project “Supercritical Water Reactor-Fuel Qualification Test”: Summary of General Corrosion Tests
Radek Novotný,
e-mail: Radek.Novotny@ec.europa.eu
Radek Novotný
1
European Commission, Joint Research Centre, Institute for Energy and Transport
, Westerduinweg 3, 1755 LE Petten
, The Netherlands
e-mail: Radek.Novotny@ec.europa.eu
1Corresponding author.
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Přemysl Janík,
e-mail: janikpremek@gmail.com
Přemysl Janík
European Space Research and Technology Centre
, Postbus 299, 2200 AG Noordwijk
, The Netherlands
e-mail: janikpremek@gmail.com
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Aki Toivonen,
e-mail: Aki.Toivonen@vtt.fi
Aki Toivonen
VTT Technical Research Centre of Finland Ltd.
, P.O. Box 1000, FI-02044 VTT
, Finland
e-mail: Aki.Toivonen@vtt.fi
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Anna Ruiz,
e-mail: Anna.Ruiz@ec.europa.eu
Anna Ruiz
European Commission, Joint Research Centre, Institute for Energy and Transport
, Westerduinweg 3, 1755 LE Petten
, The Netherlands
e-mail: Anna.Ruiz@ec.europa.eu
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Zoltan Szaraz,
e-mail: Zoltan.Szaraz@ec.europa.eu
Zoltan Szaraz
European Commission, Joint Research Centre, Institute for Energy and Transport
, Westerduinweg 3, 1755 LE Petten
, The Netherlands
e-mail: Zoltan.Szaraz@ec.europa.eu
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Lefu Zhang,
e-mail: lfzhang@sjtu.edu.cn
Lefu Zhang
School of Nuclear Science and Engineering, Shanghai Jiao Tong University
, No. 800, Dong Chuan Road, 200240 Shanghai
, China
e-mail: lfzhang@sjtu.edu.cn
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Jan Siegl,
e-mail: Jan.Siegl@fjfi.cvut.cz
Jan Siegl
Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University Prague
, Trojanova 13, 120 00 Praha 2
, Czech Republic
e-mail: Jan.Siegl@fjfi.cvut.cz
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Petr Haušild,
e-mail: Petr.Hausild@fjfi.cvut.cz
Petr Haušild
Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University Prague
, Trojanova 13, 120 00 Praha 2
, Czech Republic
e-mail: Petr.Hausild@fjfi.cvut.cz
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Sami Penttilä,
e-mail: Sami.Penttilä@vtt.fi
Sami Penttilä
VTT Technical Research Centre of Finland Ltd.
, P.O. Box 1000, FI-02044 VTT
, Finland
e-mail: Sami.Penttilä@vtt.fi
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Jan Macák
Jan Macák
Power Engineering Department,
e-mail: Jan.Macak@vscht.cz
Institute of Chemical Technology
, Technicka 3, 166 28 Prague 6
, Czech Republic
e-mail: Jan.Macak@vscht.cz
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Radek Novotný
European Commission, Joint Research Centre, Institute for Energy and Transport
, Westerduinweg 3, 1755 LE Petten
, The Netherlands
e-mail: Radek.Novotny@ec.europa.eu
Přemysl Janík
European Space Research and Technology Centre
, Postbus 299, 2200 AG Noordwijk
, The Netherlands
e-mail: janikpremek@gmail.com
Aki Toivonen
VTT Technical Research Centre of Finland Ltd.
, P.O. Box 1000, FI-02044 VTT
, Finland
e-mail: Aki.Toivonen@vtt.fi
Anna Ruiz
European Commission, Joint Research Centre, Institute for Energy and Transport
, Westerduinweg 3, 1755 LE Petten
, The Netherlands
e-mail: Anna.Ruiz@ec.europa.eu
Zoltan Szaraz
European Commission, Joint Research Centre, Institute for Energy and Transport
, Westerduinweg 3, 1755 LE Petten
, The Netherlands
e-mail: Zoltan.Szaraz@ec.europa.eu
Lefu Zhang
School of Nuclear Science and Engineering, Shanghai Jiao Tong University
, No. 800, Dong Chuan Road, 200240 Shanghai
, China
e-mail: lfzhang@sjtu.edu.cn
Jan Siegl
Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University Prague
, Trojanova 13, 120 00 Praha 2
, Czech Republic
e-mail: Jan.Siegl@fjfi.cvut.cz
Petr Haušild
Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University Prague
, Trojanova 13, 120 00 Praha 2
, Czech Republic
e-mail: Petr.Hausild@fjfi.cvut.cz
Sami Penttilä
VTT Technical Research Centre of Finland Ltd.
, P.O. Box 1000, FI-02044 VTT
, Finland
e-mail: Sami.Penttilä@vtt.fi
Jan Macák
Power Engineering Department,
e-mail: Jan.Macak@vscht.cz
Institute of Chemical Technology
, Technicka 3, 166 28 Prague 6
, Czech Republic
e-mail: Jan.Macak@vscht.cz
1Corresponding author.
Manuscript received May 26, 2015; final manuscript received January 21, 2016; published online June 17, 2016. Assoc. Editor: Thomas Schulenberg.
ASME J of Nuclear Rad Sci. Jul 2016, 2(3): 031007 (10 pages)
Published Online: June 17, 2016
Article history
Received:
May 26, 2015
Revision Received:
January 21, 2016
Accepted:
January 21, 2016
Citation
Novotný, R., Janík, P., Toivonen, A., Ruiz, A., Szaraz, Z., Zhang, L., Siegl, J., Haušild, P., Penttilä, S., and Macák, J. (June 17, 2016). "European Project “Supercritical Water Reactor-Fuel Qualification Test”: Summary of General Corrosion Tests." ASME. ASME J of Nuclear Rad Sci. July 2016; 2(3): 031007. https://doi.org/10.1115/1.4032871
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