Conveners
5.8 Structural Materials
- Aleksandr Sorokin (SSC RF-IPPE)
- Sung Ho Kim (Korea Atomic Energy Research Institute (KAERI))
Dr
Sung Ho Kim
(KAERI)
29/06/2017, 08:00
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Ferritc/martensitic steels are being considered as cladding materials for PGSFR. So KAERI has developed cladding material (FC92) which has superior thermal creep property to HT9. In order to verify the performance of cladding tube, KAERI has manufactured FC92 cladding tube in connection of the steelmaking industry. Out-of pile tests like mechanical tests (uniaxial tensile, biaxial burst,...
Prof.
Boris Margolin
(Central Research Institute of Structural Materials "Prometey")
29/06/2017, 08:20
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The present paper overviews the basic principles of Russian Standard elaborated for justification of lifetime prolongation of BN-600 fast reactor (FR) and for justification of design lifetime of BN-800 FR. These principles are based on the analysis of the main mechanisms of material damage under service and formulation of the limit conditions for different components of FR of BN type....
Mr
arnaud courcelle
(CEA Saclay)
29/06/2017, 08:40
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
In the framework of the sodium fast-reactor (SFR) project ASTRID, an optimized austenitic steel 15%Cr-15%Ni stabilized with titanium was chosen for the fuel-pin cladding. Besides irradiation swelling, one of the main issue of irradiated austenitic steels in fast reactor is the embrittlement at high temperature (>600°C).
To investigate the long-term behaviour of cladding material...
Mr
CLEMENT RAVI CHANDAR SOWRINATHAN
(INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH)
29/06/2017, 09:00
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Ferroboron has been identified as a candidate material for in–vessel radiation shielding application in future Fast Breeder Reactors (FBRs) in India that can result in significant cost savings. Out-of-pile physical and chemical characterisation studies have established its neutron shielding property and long-term compatibility with 304L SS clad under sodium at the operating temperatures. An...
Dr
Andrey Buchatsky
(CRISM "Prometey")
29/06/2017, 09:20
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Early the physical-and-mechanical model of integranular fracture has been developed that allows the prediction of creep-rupture properties of austenitic stainless steels at different neutron fluxes and temperatures. The model is based on the equations of void nucleation and growth on grain boundaries caused by inelastic deformation (creep and plastic strain) and diffusion of vacancies. The...
Mr
David LALLEMAND
(AREVA NP),
Laetitia NICOLAS
(AREVA), Dr
Thosrten MARLAUD
(AREVA NP)
29/06/2017, 09:40
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
CEA has been involved since 2006 in a substantial effort on the ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) conceptual design, mainly in cooperation with EDF, as experienced Sodium-cooled Fast Reactor (SFR) operator, and AREVA, as experienced SFR Nuclear Island and components engineering company. Whereas previous SFRs were designed for 30 or 40 years lifetime,...
