TY - GEN
T1 - Coupled neutronics and thermal hydraulics modelling in reactor dynamics codes TRAB-3d and hextran
AU - Kyrki-Rajamäki, Riitta
AU - Räty, Hanna
PY - 1999
Y1 - 1999
N2 - The reactor dynamics codes for transient and accident
analyses inherently include the coupling of neutronics
and thermal hydraulics modelling. In Finland a number of
codes with 1D and 3D neutronic models have been
developed, which include models also for the cooling
circuits. They have been used mainly for the needs of
Finnish power plants, but some of the codes have also
been utilized elsewhere. The continuous validation,
simultaneous development, and experiences obtained in
commercial applications have considerably improved the
performance and range of application of the codes. The
fast operation of the codes has enabled realistic
analysis of 3D core combined to a full model of the
cooling circuit even in such long reactivity scenarios as
ATWS.
The reactor dynamics methods are developed further and
new more detailed models are created for tasks related to
increased safety requirements. For thermal hydraulics
calculations, an accurate general flow model based on a
new solution method has been developed. Although mainly
intended for analysis purposes, the reactor dynamics
codes also provide reference solutions for simulator
applications. As computer capability increases, these
more sophisticated methods can be taken into use also in
simulator environments.
AB - The reactor dynamics codes for transient and accident
analyses inherently include the coupling of neutronics
and thermal hydraulics modelling. In Finland a number of
codes with 1D and 3D neutronic models have been
developed, which include models also for the cooling
circuits. They have been used mainly for the needs of
Finnish power plants, but some of the codes have also
been utilized elsewhere. The continuous validation,
simultaneous development, and experiences obtained in
commercial applications have considerably improved the
performance and range of application of the codes. The
fast operation of the codes has enabled realistic
analysis of 3D core combined to a full model of the
cooling circuit even in such long reactivity scenarios as
ATWS.
The reactor dynamics methods are developed further and
new more detailed models are created for tasks related to
increased safety requirements. For thermal hydraulics
calculations, an accurate general flow model based on a
new solution method has been developed. Although mainly
intended for analysis purposes, the reactor dynamics
codes also provide reference solutions for simulator
applications. As computer capability increases, these
more sophisticated methods can be taken into use also in
simulator environments.
M3 - Conference article in proceedings
SN - 951-38-5269-5
T3 - VTT Symposium
SP - 292
EP - 305
BT - Proceedings of the 2nd CSNI Specialist Meeting on Simulators and Plant Analysers
PB - VTT Technical Research Centre of Finland
CY - Espoo
T2 - 2nd CSNI Specialist Meeting on Simulators and Plant Analysers
Y2 - 29 September 1997 through 2 October 1997
ER -