The design and utilization of a high-temperature helium loop and other facilities for the study of advanced gas-cooled reactors in the Czech Republic. (November 2015)

• Record Type: Journal Article
• Authors: Berka, Jan; Hlinčík, Tomáš; Víden, Ivan; Hudský, Tomáš; Vít, Jan
• Is Part Of: Progress in nuclear energy. Volume 85(2015:Nov.)
• Page Start: 156
• Page End: 163
• Publication Date: 2015-11
• Subjects: Helium experimental loop -- High temperature reactor -- Gas fast reactor -- High temperature materials; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 333.7924
• DOI: 10.1016/j.pnucene.2015.06.003
• Languages: English
• ISSNs: 0149-1970

Abstract

Abstract: This paper focuses on the research infrastructure of advanced gas cooled reactors in the Czech Republic, particularly on the high-temperature helium loop HTHL, which is a unique facility of its kind. HTHL is intended mainly for testing structural materials. It also can be used to research technologies relating to helium coolant. The maximum temperature and pressure that can be used within the specimen testing space are 900 °C and 7 MPa, respectively, and the maximum gas flow rate in the main loop is 38 kg/hr. Originally, the equipment was envisaged as a device for corrosion tests of materials in the reactor LVR-15 but, according to current plans, a different equipment will be built for this purpose within the frame of the SUSEN project. At the same time, an additional helium loop (S-Allegro) will be built to test selected components of advanced gas-cooled reactors. Graphical abstract: Highlights: High temperature helium loop design, experience and usage. Materials tested within Czech HTR program. Other devices for HTR investigation under construction.