The safety issues of the SFRs are important due to the fact that it uses sodium as a nuclear coolant, reacting vigorously with water and air. For that reason, there are efforts to seek for alternative candidates of liquid metal coolants having excellent heat transfer property and to adopt improved safety features to the SFR concepts. This study considers gallium as alternative liquid metal coolant applicable to safety features in terms of chemical activity issue of the sodium and aims to experimentally investigate the natural convection capability of gallium as a feasibility study for the development of gallium-based passive safety features in SFRs. In this paper, the design and construction of the liquid gallium natural convection loop wer...
This paper summarizes the basis for the solution of heat removal by natural convection from both con...
The purpose of this study is to investigate the interaction between austenitic stainless steel, AISI...
In hypothetical core disruptive accident (HCDA) of a sodium-cooled fast reactor (SFR) as a severe ac...
To confirm the feasibility of the gallium-water IVR-ERVCS (in-vessel retention-external reactor vess...
Employing a gallium-based passive decay heat removal system (PDHRS), which enables the use of water ...
After the Fukushima accident, the concerns on nuclear safety are increasing more than ever before. I...
In this paper, a new approach replacing the ERVC coolant by a liquid metal instead of water is studi...
The unusual operating conditions of nuclear power reactors necessitate the use of unusual coolants. ...
International audienceThermal management became the limiting factor in the development of high power...
The present work ultimately aims to develop the IVR-ERVC (In-Vessel Retention through External React...
Nanofluids (nanoparticle colloidal suspensions) are nanotechnology-based fluids engineered for enhan...
Recently, molten salt has received attention as a promising coolant for advanced nuclear reactors, e...
The purpose of this study is to model the interaction between austenitic stainless steel and liquid ...
A facility designed and constructed to demonstrate the viability of natural convection passive heat ...
The safe operation of nuclear reactors cooled by liquid metal is an important issue to be addressed ...
This paper summarizes the basis for the solution of heat removal by natural convection from both con...
The purpose of this study is to investigate the interaction between austenitic stainless steel, AISI...
In hypothetical core disruptive accident (HCDA) of a sodium-cooled fast reactor (SFR) as a severe ac...
To confirm the feasibility of the gallium-water IVR-ERVCS (in-vessel retention-external reactor vess...
Employing a gallium-based passive decay heat removal system (PDHRS), which enables the use of water ...
After the Fukushima accident, the concerns on nuclear safety are increasing more than ever before. I...
In this paper, a new approach replacing the ERVC coolant by a liquid metal instead of water is studi...
The unusual operating conditions of nuclear power reactors necessitate the use of unusual coolants. ...
International audienceThermal management became the limiting factor in the development of high power...
The present work ultimately aims to develop the IVR-ERVC (In-Vessel Retention through External React...
Nanofluids (nanoparticle colloidal suspensions) are nanotechnology-based fluids engineered for enhan...
Recently, molten salt has received attention as a promising coolant for advanced nuclear reactors, e...
The purpose of this study is to model the interaction between austenitic stainless steel and liquid ...
A facility designed and constructed to demonstrate the viability of natural convection passive heat ...
The safe operation of nuclear reactors cooled by liquid metal is an important issue to be addressed ...
This paper summarizes the basis for the solution of heat removal by natural convection from both con...
The purpose of this study is to investigate the interaction between austenitic stainless steel, AISI...
In hypothetical core disruptive accident (HCDA) of a sodium-cooled fast reactor (SFR) as a severe ac...