European Project “Supercritical Water Reactor-Fuel Qualification Test”: Summary of General Corrosion Tests

Author:

Novotný Radek1,Janík Přemysl2,Toivonen Aki3,Ruiz Anna1,Szaraz Zoltan1,Zhang Lefu4,Siegl Jan5,Haušild Petr5,Penttilä Sami3,Macák Jan6

Affiliation:

1. European Commission, Joint Research Centre, Institute for Energy and Transport, Westerduinweg 3, 1755 LE Petten, The Netherlands e-mail:

2. European Space Research and Technology Centre, Postbus 299, 2200 AG Noordwijk, The Netherlands e-mail:

3. VTT Technical Research Centre of Finland Ltd., P.O. Box 1000, FI-02044 VTT, Finland e-mail:

4. School of Nuclear Science and Engineering, Shanghai Jiao Tong University, No. 800, Dong Chuan Road, 200240 Shanghai, China e-mail:

5. Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University Prague, Trojanova 13, 120 00 Praha 2, Czech Republic e-mail:

6. Power Engineering Department, Institute of Chemical Technology, Technicka 3, 166 28 Prague 6, Czech Republic e-mail:

Abstract

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: 316L<347H<08Cr18Ni10Ti. 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.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

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