Innovative Gen-II/III and research reactors’ fuels and materials

This manuscript presents important material challenges regarding innovative Gen-II/III nuclear systems and research reactors. The challenges are discussed alongside the key achievements so far realised within the framework of 4 EU-funded projects: H2020 IL TROVATORE, FP7 MULTIMETAL, FP7 MATTER and FP7 SCWR-FQT. | Innovative Gen-II III and research reactors fuels and materials EPJ Nuclear Sci. Technol. 6 41 2020 Nuclear Sciences P. Agostini et al. published by EDP Sciences 2020 amp Technologies https epjn 2019008 Available online at https REVIEW ARTICLE Innovative Gen-II III and research reactors fuels and materials Pietro Agostini1 Marco Utili1 Konstantza Lambrinou2 Heikki Keinänen3 Paivi Karjalainen-Roikonen3 and Mariana Arnoult Ruzickova4 1 ENEA-FSN-ING Division . Brasimone 40032 Camugnano Italy 2 NMS Institute SCK CEN Boeretang 200 2400 Mol Belgium 3 BA2505 Structural Integrity VTT Technical Research Centre of Finland Ltd. Kivimiehentie 3 Espoo Finland 4 Power Engineering Technologies Department Centrum v yzkumu Řež Hlavní 130 258 65 Husinec Řež Czech Republic Received 5 April 2019 Accepted 16 June 2019 Abstract. This manuscript presents important material challenges regarding innovative Gen-II III nuclear systems and research reactors. The challenges are discussed alongside the key achievements so far realised within the framework of 4 EU-funded projects H2020 IL TROVATORE FP7 MULTIMETAL FP7 MATTER and FP7 SCWR-FQT. All the four Projects deal with innovative researches on materials to enhance the safety of nuclear reactors. IL TROVATORE proposes new materials for fuel cladding of PWR reactors and tests in order to really find out an Accident Tolerant Fuel ATF . MULTIMETAL focused on optimization of dissimilar welds fabrication having considered the field performances and dedicated experiments. MATTER carried on methodological and experimental studies on the use of grade 91 steel in the harsh environment of liquid metal cooled EU fast reactors. SCWR-FQT focused on fuel qualification of Supercritical Water Reactor including the selection of the better material to resist the associated high thermal flux. 1 Introduction LWRs and validate them in an industrially relevant environment via a dedicated neutron irradiation in PWR- The 2011 Fukushima

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