TY - CHAP
T1 - Reactor physics and dynamics (READY)
T2 - READY summary report
AU - Räty, Hanna
AU - Daavittila, Antti
PY - 2002
Y1 - 2002
N2 - 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. Validation of VTT's three-dimensional BWR dynamics code has
been completed, and analyses with three-dimensional core models can be
carried out for PWR, BWR and VVER type reactors. Until now, the transient
analyses for BWRs have been done with one-dimensional models. Fuel models of
the dynamics codes have been improved, and USNRC's fuel behaviour code has
been coupled with VTT's advanced hydraulics model. The coupled code has been
delivered to USA in agreement with USNRC. Development and application of a
sophisticated hydraulics solver in reactor dynamics has resulted in a BWR
circuit model that has been tested in steady state calculations.
AB - 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. Validation of VTT's three-dimensional BWR dynamics code has
been completed, and analyses with three-dimensional core models can be
carried out for PWR, BWR and VVER type reactors. Until now, the transient
analyses for BWRs have been done with one-dimensional models. Fuel models of
the dynamics codes have been improved, and USNRC's fuel behaviour code has
been coupled with VTT's advanced hydraulics model. The coupled code has been
delivered to USA in agreement with USNRC. Development and application of a
sophisticated hydraulics solver in reactor dynamics has resulted in a BWR
circuit model that has been tested in steady state calculations.
M3 - Chapter or book article
SN - 951-38-6085-X
T3 - VTT Tiedotteita - Research Notes
SP - 113
EP - 126
BT - FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002
PB - VTT Technical Research Centre of Finland
CY - Espoo
ER -