Computer modeling codes represent a crucial tool to support the design of future fusion plants. Since one of the most important functions that codes must achieve is assessing safety systems design, a verification and validation phase is required. In this framework, a code-to-code comparison among four codes has been carried within EUROfusion consortium between Safety Analyses and Environment and Balance of Plant work packages. In particular, an in-vessel Loss of Coolant Accident has been selected as a benchmark scenario for investigating thermal-hydraulic parameters of the vacuum vessel and its suppression system. This paper aims to compare the answer of different codes in terms of peak pressure within the vacuum vessel and its timing, the...
International audienceThe CATHARE code is a thermal-hydraulic code employed by several countries in ...
The large volume vacuum systems are used in many industrial operations and research laboratories. Ac...
The OECD/NEA PSB-VVER project provided unique and useful experimental data from the large-scale PSB-...
Computer modeling codes represent a crucial tool to support the design of future fusion plants. Sinc...
Accidental transients in fusion reactors, such as the in-vessel Loss-of-Coolant Accident (LOCA) cons...
One of the accidents to be analyzed for the operation of the EU DEMO tokamak reactor is the in-vesse...
In the nuclear field, the correct evaluation of the effects of design-basis accidents is fundamental...
In order to evaluate plasma evolution and in-vessel components strains, a safety code called AINA ha...
Code validation activities have been promoted inside the EFDA (European Fusion Development Agreement...
Dust re-suspension as a consequences of loss of vacuum accident (LOVA) or loss of coolant accident (...
Code validation activities have been promoted inside the European fusion development agreement (EFDA...
Thermohydraulic analysis of postulated accidents will identify system responses to accident scenario...
A 2-inch, cold-leg loss-of-coolant accident (LOCA) in a 900 MWe generic Western PWR was simulated us...
The large volume vacuum systems are used in many industrial operations and research laboratories. Ac...
This paper presents assessment of the capacity of W7-X venting system in response to in-vessel LOCA,...
International audienceThe CATHARE code is a thermal-hydraulic code employed by several countries in ...
The large volume vacuum systems are used in many industrial operations and research laboratories. Ac...
The OECD/NEA PSB-VVER project provided unique and useful experimental data from the large-scale PSB-...
Computer modeling codes represent a crucial tool to support the design of future fusion plants. Sinc...
Accidental transients in fusion reactors, such as the in-vessel Loss-of-Coolant Accident (LOCA) cons...
One of the accidents to be analyzed for the operation of the EU DEMO tokamak reactor is the in-vesse...
In the nuclear field, the correct evaluation of the effects of design-basis accidents is fundamental...
In order to evaluate plasma evolution and in-vessel components strains, a safety code called AINA ha...
Code validation activities have been promoted inside the EFDA (European Fusion Development Agreement...
Dust re-suspension as a consequences of loss of vacuum accident (LOVA) or loss of coolant accident (...
Code validation activities have been promoted inside the European fusion development agreement (EFDA...
Thermohydraulic analysis of postulated accidents will identify system responses to accident scenario...
A 2-inch, cold-leg loss-of-coolant accident (LOCA) in a 900 MWe generic Western PWR was simulated us...
The large volume vacuum systems are used in many industrial operations and research laboratories. Ac...
This paper presents assessment of the capacity of W7-X venting system in response to in-vessel LOCA,...
International audienceThe CATHARE code is a thermal-hydraulic code employed by several countries in ...
The large volume vacuum systems are used in many industrial operations and research laboratories. Ac...
The OECD/NEA PSB-VVER project provided unique and useful experimental data from the large-scale PSB-...