In the sodium fast reactors envisioned in the Generation IV program, fuel pins are expected to be irradiated at a higher temperature up to a higher burnup. Integrity of these fuel pins strongly depends on whether the cladding can withstand such irradiation environments. As for the cladding, it is preferred to have a low swelling and high ductility for its lifetime. Sufficient creep strengths at a high temperature are required. The materials for the duct require sufficient strength and toughness to make a duct handling possible after an irradiation. This paper describes the main factors controlling the lifetime of these materials, and the viability of the currently available materials for their utilization in the core materials of GEN-IV SFR...
The Sodium-cooled Fast Reactor(SFR) is one of the six promising nuclear energy systems for future pr...
Available information on the corrosion behavior and mechanical properties of structural materials in...
International audienceThe fuel pin bundles of Sodium-cooled Fast Reactors (SFR) undergo significant ...
The main challenge for fuels for future Sodium Fast Reactor systems is the development and qualifica...
This report documents Final Year Project No. A1076-141, Investigation on the sodium cooled fast reac...
Development of advanced materials along with improved high temperature mechanical properties, partic...
An expert panel was assembled to identify gaps in fuels and materials research prior to licensing so...
AbstractMetal fuel is being developed for the prototype generation-IV sodium-cooled fast reactor (PG...
The alloys 316L(N) and Mod. 9Cr-1Mo steel are the major structural materials for fabrication of stru...
The design of innovative cores for Generation IV Sodium-cooled Fast Reactors (SFRs) must chiefly foc...
According to the Generation IV International Forum Technology Roadmap, Sodium Fast Reactors (SFR) co...
The swelling, corrosion and high-temperature embrittlement behavior of the fast-neutron sodium-coole...
Metal fuel is being developed for the prototype generation-IV sodium-cooled fast reactor (PGSFR) to ...
AbstractAustenitic stainless steels (SS) with appropriate mechanical and irradiation-resistant prope...
Abstract. Fast breeder reactors (FBRs) are destined to play a crucial role in the Indian nuclear pow...
The Sodium-cooled Fast Reactor(SFR) is one of the six promising nuclear energy systems for future pr...
Available information on the corrosion behavior and mechanical properties of structural materials in...
International audienceThe fuel pin bundles of Sodium-cooled Fast Reactors (SFR) undergo significant ...
The main challenge for fuels for future Sodium Fast Reactor systems is the development and qualifica...
This report documents Final Year Project No. A1076-141, Investigation on the sodium cooled fast reac...
Development of advanced materials along with improved high temperature mechanical properties, partic...
An expert panel was assembled to identify gaps in fuels and materials research prior to licensing so...
AbstractMetal fuel is being developed for the prototype generation-IV sodium-cooled fast reactor (PG...
The alloys 316L(N) and Mod. 9Cr-1Mo steel are the major structural materials for fabrication of stru...
The design of innovative cores for Generation IV Sodium-cooled Fast Reactors (SFRs) must chiefly foc...
According to the Generation IV International Forum Technology Roadmap, Sodium Fast Reactors (SFR) co...
The swelling, corrosion and high-temperature embrittlement behavior of the fast-neutron sodium-coole...
Metal fuel is being developed for the prototype generation-IV sodium-cooled fast reactor (PGSFR) to ...
AbstractAustenitic stainless steels (SS) with appropriate mechanical and irradiation-resistant prope...
Abstract. Fast breeder reactors (FBRs) are destined to play a crucial role in the Indian nuclear pow...
The Sodium-cooled Fast Reactor(SFR) is one of the six promising nuclear energy systems for future pr...
Available information on the corrosion behavior and mechanical properties of structural materials in...
International audienceThe fuel pin bundles of Sodium-cooled Fast Reactors (SFR) undergo significant ...