International audienceASTEC-Na is a computer code system which evaluates protected and unprotected accidents in Sodium-cooled Fast Reactors throughout the Initiation Phase. The fuel pin behavior models implemented in ASTEC-Na simulate the essential aspects of the thermal and mechanical behavior of SFR fuel pins in nominal and accidental conditions. Besides the improvement of existing ASTEC-Na models, a specific cladding mechanical model and an in-pin fuel relocation model have been developed during the JASMIN project, where the latter has been already implemented in the code. ASTEC-Na fuel pin behavior models are described in this paper and their transient predictions for four CABRI transient tests are compared to available experimental dat...
To improve the capability of the SAS4A code, which simulates the initiating phase of core disruptive...
This work concerns the assessment of the consequences of a Loss Of Coolant Accident (LOCA) and an Un...
Two three-pin cluster tests simulating the Unprotected Loss-of-Flow (ULOF) accident of Sodiumcooled ...
International audienceASTEC-Na is a computer code system which evaluates protected and unprotected a...
ASTEC-Na is a computer code system which evaluates protected and unprotected accidents in Sodium-coo...
The 4-year JASMIN collaborative project, involving 9 organizations, was launched by IRSN end of 2011...
The EU-JASMIN project (7th FP of EURATOM) has been centred on the development and validation of the ...
Within the framework of the European JASMIN project, the ASTEC-Na code is being developed for safet...
The Institute for Energy and Transport (IET) in collaboration with the project partners is conductin...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactor (SFR) in ...
AbstractThis paper presents simulation results of the CABRI BI1 test using the code ASTEC-Na, curren...
ISBN : 9781510872622International audienceWithin the framework of the Generation IV Sodium-cooled Fa...
This paper describes the work performed within the WP2.1 of the JASMIN project to validate the therm...
To improve the capability of the SAS4A code, which simulates the initiating phase of core disruptive...
This work concerns the assessment of the consequences of a Loss Of Coolant Accident (LOCA) and an Un...
Two three-pin cluster tests simulating the Unprotected Loss-of-Flow (ULOF) accident of Sodiumcooled ...
International audienceASTEC-Na is a computer code system which evaluates protected and unprotected a...
ASTEC-Na is a computer code system which evaluates protected and unprotected accidents in Sodium-coo...
The 4-year JASMIN collaborative project, involving 9 organizations, was launched by IRSN end of 2011...
The EU-JASMIN project (7th FP of EURATOM) has been centred on the development and validation of the ...
Within the framework of the European JASMIN project, the ASTEC-Na code is being developed for safet...
The Institute for Energy and Transport (IET) in collaboration with the project partners is conductin...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactor (SFR) in ...
AbstractThis paper presents simulation results of the CABRI BI1 test using the code ASTEC-Na, curren...
ISBN : 9781510872622International audienceWithin the framework of the Generation IV Sodium-cooled Fa...
This paper describes the work performed within the WP2.1 of the JASMIN project to validate the therm...
To improve the capability of the SAS4A code, which simulates the initiating phase of core disruptive...
This work concerns the assessment of the consequences of a Loss Of Coolant Accident (LOCA) and an Un...
Two three-pin cluster tests simulating the Unprotected Loss-of-Flow (ULOF) accident of Sodiumcooled ...