As a result of upgrading, adapting, developing and validating several reactor physics and dynamics codes of VTT's code system more accurate calculations and predictions of physical phenomena can now be performed. Three-dimensional reactor physics codes have been introduced and validated for various applications, especially for out-of-core flux, criticality safety, and dose rate calculations. A multi-temperature MCNP cross section and scattering law library has been created. Most recently Monte Carlo technique has been applied in burnup calculations. Development of a new advanced nodal model has resulted in a highly promising new BWR simulator code, ensuring independent calculational capabilities for steady state and safety analyses. Validat...
To simulate reactor transients for safety analysis with the Monte Carlo method the generation and de...
Coupling the three-dimensional Analytic Function Expansion Nodal (AFEN) nodal model [1, 2] developed...
To simulate reactor transients for safety analysis with the Monte Carlo method the generation and de...
VTT maintains and further developes a comprehensive safety analysis code system ranging from the bas...
VTT maintains and further developes a comprehensive safety analysis code system ranging from the bas...
VTT maintains and further developes a comprehensive safety analysis code system ranging from the bas...
A three-dimensional reactor dynamics computer code has been developed, validated and applied for tra...
A three-dimensional reactor dynamics computer code has been developed, validated and applied for tra...
TRAB-3D is the newest member in the reactor dynamics code family developed in VTT. It is now possibl...
TRAB-3D is the newest member in the reactor dynamics code family developed in VTT. It is now possibl...
New generation nuclear reactors are designed using advanced safety analysis methods. A thorough unde...
TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit the...
TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit the...
Recently, three-dimensional neutron-kinetics core models have been coupled to advanced thermal-hydra...
Coupling the three-dimensional Analytic Function Expansion Nodal (AFEN) nodal model [1, 2] developed...
To simulate reactor transients for safety analysis with the Monte Carlo method the generation and de...
Coupling the three-dimensional Analytic Function Expansion Nodal (AFEN) nodal model [1, 2] developed...
To simulate reactor transients for safety analysis with the Monte Carlo method the generation and de...
VTT maintains and further developes a comprehensive safety analysis code system ranging from the bas...
VTT maintains and further developes a comprehensive safety analysis code system ranging from the bas...
VTT maintains and further developes a comprehensive safety analysis code system ranging from the bas...
A three-dimensional reactor dynamics computer code has been developed, validated and applied for tra...
A three-dimensional reactor dynamics computer code has been developed, validated and applied for tra...
TRAB-3D is the newest member in the reactor dynamics code family developed in VTT. It is now possibl...
TRAB-3D is the newest member in the reactor dynamics code family developed in VTT. It is now possibl...
New generation nuclear reactors are designed using advanced safety analysis methods. A thorough unde...
TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit the...
TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit the...
Recently, three-dimensional neutron-kinetics core models have been coupled to advanced thermal-hydra...
Coupling the three-dimensional Analytic Function Expansion Nodal (AFEN) nodal model [1, 2] developed...
To simulate reactor transients for safety analysis with the Monte Carlo method the generation and de...
Coupling the three-dimensional Analytic Function Expansion Nodal (AFEN) nodal model [1, 2] developed...
To simulate reactor transients for safety analysis with the Monte Carlo method the generation and de...