New nuclear advanced facilities at CVREZ

• Autorzy: Arnoult X.C. , Zychova M. , Ruzickova M. , Berka J. , Di Gabriele F. , Srba O.
• Języki publikacji: EN

Abstrakty

EN

Purpose: The goal of this paper is to present the facilities designed and built in the frame of the SUSEN program in the Centrum Výzkumu Řež, allowing research and development in the area of Generation IV and nuclear fusion reactors. Design/methodology/approach: The coolants investigated are: supercritical water, helium and lead-bismuth. The SSD team is in charge to perform in hot-cells various kinds of mechanical tests on irradiated materials in the range from room temperature to 800°C (tensile test, creep test, tension-torsion test and fatigue test in different type of loading) and microstructure investigation with SEM and TEM. Findings: SUSEN project allows at CVREZ to develop the facilities and instrumentations that institute has already had. This project allows also developing new facilities, buying new experimental machines and gives a wide range of investigation in different field in the research and development of Gen IV reactor. Research limitations/implications: The different types of loops study the impact of media on the properties of structural materials. The behavior of media and the different type of mechanical tests in static and fatigue regime at different temperatures enable to extend the limit of knowledge about mechanisms of corrosion, mechanisms of degradations and improve the design and safety in nuclear power plant. Originality/value: The SUSEN program is divided in four sub-programs and teams: Technological Experimental Circuits (TEC), Structural and System Diagnostics (SSD), Material Research (MAT) and Material Fuel Cycle (JPC). TEC team is in charge of the development large-scale experimental loops to improve the quality and quantity of data about the behavior of coolants used in the primary circuit and the corrosion of steel in contact with coolants.

Słowa kluczowe

EN

mechanical test; high temperature; corrosion; loops

PL

badania wytrzymałościowe; temperatura wysoka; korozja; pętle

• Wydawca: International OCSCO World Press
• Czasopismo: Journal of Achievements in Materials and Manufacturing Engineering
• Rocznik: 2014
• Tom: Vol. 65, nr 2
• Strony: 86--92
• Opis fizyczny: Bibliogr. 10 poz., rys.

Twórcy

autor

Arnoult X.C.

• Centrum Výzkumu Řež, Hlavni 130, 250 68 Husinec-Rez, Czech Republic

autor

Zychova M.

• Centrum Výzkumu Řež, Hlavni 130, 250 68 Husinec-Rez, Czech Republic

autor

Ruzickova M.

• Centrum Výzkumu Řež, Hlavni 130, 250 68 Husinec-Rez, Czech Republic

autor

Berka J.

• Centrum Výzkumu Řež, Hlavni 130, 250 68 Husinec-Rez, Czech Republic

autor

Di Gabriele F.

• Centrum Výzkumu Řež, Hlavni 130, 250 68 Husinec-Rez, Czech Republic

autor

Srba O.

• Centrum Výzkumu Řež, Hlavni 130, 250 68 Husinec-Rez, Czech Republic

Bibliografia

• [1] http://susen2020.cz/
• [2] https://www.gen-4.org/gif/jcms/c_9260/public
• [3] M. Zychova, et al., New research infrastructure for SCWR in Centrum Vyzkumu Rez, Proceedings of the 6th International Symposium on Supercritical Water-Cooled Reactors 2013, Shenzhen, Guangdong, China.
• [4] J. Berka, J. Matěcha, M. Černý, I. Víden, F. Sus, P. Hájek, New experimental device for VHTR structural material testing and helium coolant chemistry investigation at High Temperature Helium Loop in NRI Řež, Nuclear Engineering and Design 251 (2012) 203-207.
• [5] J. Matěcha, J. Berka, F. Sus, M. Černý, J. Lengyel, V. Tekáč, Testing of analytical and purification methods for HTR helium coolant, Nuclear Engineering and Design 251 (2012) 208-215.
• [6] http://www.srigc.com/HIDman.pdf
• [7] J. Berka, I. Víden, V. Kozmík, Organické látky detegované vheliovém okruhu experimentální výzkumné aparatury k simulaci chlazení jaderného reaktoru při zahájení provozou, Chemnické listy 106/10 (2012) 980-987.
• [8] G. Ilinčev, 15 years of research in structural material corrosion resistance in liquid metals at State Research Institute for Protection of Materials in Prague, Nuclear Energy 23/85 (1977).
• [9] L. Brissonneau, F. Beauchamp, O. Morier, C. Schroer, J. Konys, A. Kobzova, F. Di Gabriele, J.-L. Courouau, Oxygen control systems and impurity purification in LBE: Learning from DEMETRA project, Journal of Nuclear Materials 415/3 (2011) 348-360.
• [10] A. Doubková, F. Di Gabriele, P. Brabec, E. Keilová, Corrosion behavior of steels in flowing lead–bismuth under abnormal conditions, Journal of Nuclear Materials 376/3 (2008) 260-264.