Using liquid sodium at high temperatures in test facilities requires defining rules specific to this technology to ensure that operations are safe and reliable. Such facilities can be operated under optimal safety conditions when a certain number of safety principles are adopted as early as the design phase. The purpose of this document is therefore to explain the safety rules to be incorporated by the designer during the definition of a project to build a facility implementing sodium at high temperature. These design rules are applicable to the various functions that the facility must provide under the best possible conditions of safety; for this reason, rules pertaining to construction or system operations are not covered in this document
The study defines a program for the development of large sodium pamps for use with sodium cooled rea...
To support development and hardware-based testing of various space reactor concepts, the Early Fligh...
The objective of this task is to identify issues relevant to ASME Section III, Subsection NH [1], an...
Generator IV and other nuclear fast reactors have historically used liquid sodium as a coolant. The ...
AbstractTwo independent sodium loops under common name INSOT facilities were constructed in Fast Rea...
AbstractTwenty sodium-cooled fast reactors (SFRs) have provided valuable experience in design, licen...
All existing sodium fast reactors, built or operated, have a safety vessel around the main reactor v...
Abstract – Due to its advantageous thermodynamic characteristics at high temperature (550 °C), liqui...
This report gives a description of the activities in design, fabrication, construction, and assembli...
International audienceFrom a general perspective generation IV (GEN IV) reactors shall excel in safe...
Standardized test facilities were developed and operate for investigating the compatibility of struc...
Liquid sodium is used as a coolant in fast breeder reactors on account of its excellent heat transfe...
Following up the previous European projects EFR and CP-ESFR, a new Horizon-2020 project, called ESFR...
AbstractThe design of Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) has been developed and the...
SIGLELD:f82/1849. / BLDSC - British Library Document Supply CentreGBUnited Kingdo
The study defines a program for the development of large sodium pamps for use with sodium cooled rea...
To support development and hardware-based testing of various space reactor concepts, the Early Fligh...
The objective of this task is to identify issues relevant to ASME Section III, Subsection NH [1], an...
Generator IV and other nuclear fast reactors have historically used liquid sodium as a coolant. The ...
AbstractTwo independent sodium loops under common name INSOT facilities were constructed in Fast Rea...
AbstractTwenty sodium-cooled fast reactors (SFRs) have provided valuable experience in design, licen...
All existing sodium fast reactors, built or operated, have a safety vessel around the main reactor v...
Abstract – Due to its advantageous thermodynamic characteristics at high temperature (550 °C), liqui...
This report gives a description of the activities in design, fabrication, construction, and assembli...
International audienceFrom a general perspective generation IV (GEN IV) reactors shall excel in safe...
Standardized test facilities were developed and operate for investigating the compatibility of struc...
Liquid sodium is used as a coolant in fast breeder reactors on account of its excellent heat transfe...
Following up the previous European projects EFR and CP-ESFR, a new Horizon-2020 project, called ESFR...
AbstractThe design of Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) has been developed and the...
SIGLELD:f82/1849. / BLDSC - British Library Document Supply CentreGBUnited Kingdo
The study defines a program for the development of large sodium pamps for use with sodium cooled rea...
To support development and hardware-based testing of various space reactor concepts, the Early Fligh...
The objective of this task is to identify issues relevant to ASME Section III, Subsection NH [1], an...