The Reduction of Radiological Consequences of design basis and extension Accidents (R2CA) is an EU H2020 project launched in
September 2019. It will run for four years and is coordinated by IRSN. The project, which is mainly funded by the
European Commission, brings together seventeen different organizations based in twelve countries.
In most current nuclear safety studies, the radiological consequences of a Loss-of-Coolant Accident (LOCA) or of a Steam Generator Tube Rupture (SGTR) accident occurring in a nuclear reactor are assessed based on 'conservative' scenarios and assumptions, which differ from one country to another.
The aim of the R2CA project is to develop new calculation methodologies and updated computer codes (integrating the evaluation of uncertainty) in order to produce more realistic evaluations of radioactive releases resulting from such accidents. These new evaluations should serve to improve accident management and propose new reactor systems instrumentation, thereby improving facility safety.
The new design methods developed will be harmonized and tested on different types of Generation II and III reactor [Pressurized Water Reactors (PWR), Boiling Water Reactors (BWR) and VVER reactors, many of which are in service in Eastern Europe, and the EPR]. In addition to acting as coordinator for the project, two IRSN departments [the Severe Accident Department (SAG) and the (Incident and Accident Control Department SEMIA)] will work on developing new models and calculation methodologies for evaluating the source term during LOCAs and improving the iodine release evaluation during SGTR sequences within design basis and design extension conditions.
The Reduction of Radiological Consequences of design basis and extension Accidents (R2CA) is an EU H2020 project launched in September 2019. It will run for four years and is coordinated by IRSN. The project, which is mainly funded by the European Commission, brings together seventeen different organizations based in twelve countries.
In most current nuclear safety studies, the radiological consequences of a Loss-of-Coolant Accident (LOCA) or of a Steam Generator Tube Rupture (SGTR) accident occurring in a nuclear reactor are assessed based on 'conservative' scenarios and assumptions, which differ from one country to another.
The aim of the R2CA project is to develop new calculation methodologies and updated computer codes (integrating the evaluation of uncertainty) in order to produce more realistic evaluations of radioactive releases resulting from such accidents. These new evaluations should serve to improve accident management and propose new reactor systems instrumentation, thereby improving facility safety.
The new design methods developed will be harmonized and tested on different types of Generation II and III reactor [Pressurized Water Reactors (PWR), Boiling Water Reactors (BWR) and VVER reactors, many of which are in service in Eastern Europe, and the EPR]. In addition to acting as coordinator for the project, two IRSN departments [the Severe Accident Department (SAG) and the (Incident and Accident Control Department SEMIA)] will work on developing new models and calculation methodologies for evaluating the source term during LOCAs and improving the iodine release evaluation during SGTR sequences within design basis and design extension conditions.
In most current nuclear safety studies, the radiological consequences of a Loss-of-Coolant Accident (LOCA) or of a Steam Generator Tube Rupture (SGTR) accident occurring in a nuclear reactor are assessed based on 'conservative' scenarios and assumptions, which differ from one country to another.
The aim of the R2CA project is to develop new calculation methodologies and updated computer codes (integrating the evaluation of uncertainty) in order to produce more realistic evaluations of radioactive releases resulting from such accidents. These new evaluations should serve to improve accident management and propose new reactor systems instrumentation, thereby improving facility safety.
The new design methods developed will be harmonized and tested on different types of Generation II and III reactor [Pressurized Water Reactors (PWR), Boiling Water Reactors (BWR) and VVER reactors, many of which are in service in Eastern Europe, and the EPR]. In addition to acting as coordinator for the project, two IRSN departments [the Severe Accident Department (SAG) and the (Incident and Accident Control Department SEMIA)] will work on developing new models and calculation methodologies for evaluating the source term during LOCAs and improving the iodine release evaluation during SGTR sequences within design basis and design extension conditions.
The Reduction of Radiological Consequences of design basis and extension Accidents (R2CA) is an EU H2020 project launched in September 2019. It will run for four years and is coordinated by IRSN. The project, which is mainly funded by the European Commission, brings together seventeen different organizations based in twelve countries.
In most current nuclear safety studies, the radiological consequences of a Loss-of-Coolant Accident (LOCA) or of a Steam Generator Tube Rupture (SGTR) accident occurring in a nuclear reactor are assessed based on 'conservative' scenarios and assumptions, which differ from one country to another.
The aim of the R2CA project is to develop new calculation methodologies and updated computer codes (integrating the evaluation of uncertainty) in order to produce more realistic evaluations of radioactive releases resulting from such accidents. These new evaluations should serve to improve accident management and propose new reactor systems instrumentation, thereby improving facility safety.
The new design methods developed will be harmonized and tested on different types of Generation II and III reactor [Pressurized Water Reactors (PWR), Boiling Water Reactors (BWR) and VVER reactors, many of which are in service in Eastern Europe, and the EPR]. In addition to acting as coordinator for the project, two IRSN departments [the Severe Accident Department (SAG) and the (Incident and Accident Control Department SEMIA)] will work on developing new models and calculation methodologies for evaluating the source term during LOCAs and improving the iodine release evaluation during SGTR sequences within design basis and design extension conditions.
