TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit thermal-hydraulics. The code, entirely developed at VTT, can be used in transient and accident analyses of boiling (BWR) and pressurized water (PWR) reactors with rectangular fuel bundle geometry. The validation history of TRAB-3D includes calculation of international benchmark exercises, as well as comparisons with measured data from real plant transients. The most recent validation case is a load rejection test performed at the Olkiluoto 1 nuclear power plant in 1998 in connection with the power uprating project. The fact that there is local power measurement data available from this test makes it a suitable case for three-dimensional core mod...
TRAB-3D models the PWR and BWR reactor core using the two-group diffusion equations in homogenised f...
As a result of upgrading, adapting, developing and validating several reactor physics and dynamics c...
As a result of upgrading, adapting, developing and validating several reactor physics and dynamics c...
TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit the...
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...
VTT's three-dimensional TRAB-3D core dynamics code and SMABRE thermal hydraulic system code have bee...
The one-dimensional reactor dynamics code TRAB (Transient Analysis code for BWRS) developed at VTT w...
VTT's three-dimensional TRAB-3D core dynamics code and SMABRE thermal hydraulic system code have bee...
The three-dimensional TRAB-3D core dynamics code is being internally coupled to the thermal hydrauli...
The three-dimensional TRAB-3D core dynamics code is being internally coupled to the thermal hydrauli...
The Transient Reactor Analysis Code (TRAC) being developed at Los Alamos National Laboratory provide...
The TRAB-SMABRE code is a result of code development efforts carried out at VTT Processes in Finland...
The TRAB-SMABRE code is a result of code development efforts carried out at VTT Processes in Finland...
The reactor dynamics codes for transient and accident analyses inherently include the coupling of ne...
TRAB-3D models the PWR and BWR reactor core using the two-group diffusion equations in homogenised f...
As a result of upgrading, adapting, developing and validating several reactor physics and dynamics c...
As a result of upgrading, adapting, developing and validating several reactor physics and dynamics c...
TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit the...
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...
VTT's three-dimensional TRAB-3D core dynamics code and SMABRE thermal hydraulic system code have bee...
The one-dimensional reactor dynamics code TRAB (Transient Analysis code for BWRS) developed at VTT w...
VTT's three-dimensional TRAB-3D core dynamics code and SMABRE thermal hydraulic system code have bee...
The three-dimensional TRAB-3D core dynamics code is being internally coupled to the thermal hydrauli...
The three-dimensional TRAB-3D core dynamics code is being internally coupled to the thermal hydrauli...
The Transient Reactor Analysis Code (TRAC) being developed at Los Alamos National Laboratory provide...
The TRAB-SMABRE code is a result of code development efforts carried out at VTT Processes in Finland...
The TRAB-SMABRE code is a result of code development efforts carried out at VTT Processes in Finland...
The reactor dynamics codes for transient and accident analyses inherently include the coupling of ne...
TRAB-3D models the PWR and BWR reactor core using the two-group diffusion equations in homogenised f...
As a result of upgrading, adapting, developing and validating several reactor physics and dynamics c...
As a result of upgrading, adapting, developing and validating several reactor physics and dynamics c...