TY - CHAP
T1 - KOTO special report
T2 - Effect of creep on fuel behaviour in RIA
AU - Knuutila, Arttu
PY - 2000
Y1 - 2000
N2 - Creep is a high temperature deformation mechanism that
becomes significant when the temperature exceeds about
half of the material absolute melting point. An earlier
study at VTT shows that creep is a significant
deformation mechanism in certain reactivity initiated
accidents (RIA). So, to be able to realistically simulate
RIA creep has to be included in the simulation.
VTT Energy is using the SCANAIR computer code to analyse
the behaviour of nuclear fuel in accident conditions. The
code is meant to simulate a reactivity-initiated accident
in a light water reactor. SCANAIR was designed to handle
the closely interconnected thermal-mechanical
calculations that are needed to simulate the accident
behaviour of a fuel rod. The code simulates the
thermal-mechanical behaviour of a single nuclear fuel rod
with numerical models. A finite element model is used in
the mechanical module of SCANAIR to simulate the
mechanical behaviour of the rod. The mechanical module is
designed to describe the highly nonlinear mechanical
behaviour of the fuel rod taking into account elasticity,
plasticity, thermal expansion, cracking, and fission gas
swelling. Also a creep model has been implemented in
SCANAIR module at VTT Energy.
This paper briefly describes the implemented creep model
in the SCANAIR code. A simple example calculation is also
made with SCANAIR to show the effect of the creep on RIA
calculation.
AB - Creep is a high temperature deformation mechanism that
becomes significant when the temperature exceeds about
half of the material absolute melting point. An earlier
study at VTT shows that creep is a significant
deformation mechanism in certain reactivity initiated
accidents (RIA). So, to be able to realistically simulate
RIA creep has to be included in the simulation.
VTT Energy is using the SCANAIR computer code to analyse
the behaviour of nuclear fuel in accident conditions. The
code is meant to simulate a reactivity-initiated accident
in a light water reactor. SCANAIR was designed to handle
the closely interconnected thermal-mechanical
calculations that are needed to simulate the accident
behaviour of a fuel rod. The code simulates the
thermal-mechanical behaviour of a single nuclear fuel rod
with numerical models. A finite element model is used in
the mechanical module of SCANAIR to simulate the
mechanical behaviour of the rod. The mechanical module is
designed to describe the highly nonlinear mechanical
behaviour of the fuel rod taking into account elasticity,
plasticity, thermal expansion, cracking, and fission gas
swelling. Also a creep model has been implemented in
SCANAIR module at VTT Energy.
This paper briefly describes the implemented creep model
in the SCANAIR code. A simple example calculation is also
made with SCANAIR to show the effect of the creep on RIA
calculation.
M3 - Chapter or book article
SN - 951-38-5750-7
T3 - VTT Tiedotteita - Research Notes
SP - 142
EP - 150
BT - FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety
PB - VTT Technical Research Centre of Finland
CY - Espoo
ER -