Add to ORKGA sodium-cooled fast reactor (SFR) is being developed at the Korea Atomic Energy Research Insti-tute (KAERI). As in-core structural material for a SFR, advanced radiation resistant ODS steel (ARROS) has been developed. This paper summarizes the current status of ARROS development regarding an ODS steel composition, fabrication technology of ODS steel structural components and key joining technologies of ODS steel structural components
This paper discusses the rationale behind the selection of materials for the different components of...
OAK B188 A Novel Approach to Materials Development for Advanced Reactor Systems. Quarterly Progress ...
International audienceOxide Dispersion Strengthened ferritic/martensitic steels are developed as fut...
As one of the Gen-IV nuclear energy systems, a sodium-cooled fast reactor (SFR) is being developed a...
AbstractAs one of the Gen-IV nuclear energy systems, a sodium-cooled fast reactor (SFR) is being dev...
AbstractKorea has put in a huge effort to develop the future nuclear systems such as a sodium-cooled...
AbstractA sodium-cooled fast reactor (SFR) and a very high temperature reactor (VHTR) are being deve...
In this paper, a description of the past and present research activities for the development of the ...
The alloys 316L(N) and Mod. 9Cr-1Mo steel are the major structural materials for fabrication of stru...
This research project involved working on the pressure resistance welding of oxide dispersion streng...
Fast breeder reactors (FBR) are essential to enhance the share of nuclear power to meet the growing ...
Oxide dispersion strengthened (ODS) steels are promising candidates for use as structural materials ...
The main challenge for fuels for future Sodium Fast Reactor systems is the development and qualifica...
An overview of the current status of development of ferritic steels for emerging fast reactor techno...
OAK B188 A Novel Approach to Material Development for Advanced Reactor Systems. Year one of this pro...
This paper discusses the rationale behind the selection of materials for the different components of...
OAK B188 A Novel Approach to Materials Development for Advanced Reactor Systems. Quarterly Progress ...
International audienceOxide Dispersion Strengthened ferritic/martensitic steels are developed as fut...
As one of the Gen-IV nuclear energy systems, a sodium-cooled fast reactor (SFR) is being developed a...
AbstractAs one of the Gen-IV nuclear energy systems, a sodium-cooled fast reactor (SFR) is being dev...
AbstractKorea has put in a huge effort to develop the future nuclear systems such as a sodium-cooled...
AbstractA sodium-cooled fast reactor (SFR) and a very high temperature reactor (VHTR) are being deve...
In this paper, a description of the past and present research activities for the development of the ...
The alloys 316L(N) and Mod. 9Cr-1Mo steel are the major structural materials for fabrication of stru...
This research project involved working on the pressure resistance welding of oxide dispersion streng...
Fast breeder reactors (FBR) are essential to enhance the share of nuclear power to meet the growing ...
Oxide dispersion strengthened (ODS) steels are promising candidates for use as structural materials ...
The main challenge for fuels for future Sodium Fast Reactor systems is the development and qualifica...
An overview of the current status of development of ferritic steels for emerging fast reactor techno...
OAK B188 A Novel Approach to Material Development for Advanced Reactor Systems. Year one of this pro...
This paper discusses the rationale behind the selection of materials for the different components of...
OAK B188 A Novel Approach to Materials Development for Advanced Reactor Systems. Quarterly Progress ...
International audienceOxide Dispersion Strengthened ferritic/martensitic steels are developed as fut...