TY - CHAP
T1 - Development and Validation of Fuel Performance Codes (POKEVA)
T2 - POKEVA summary report
AU - Kelppe, Seppo
PY - 2011
Y1 - 2011
N2 - Assessment, validation, and further development of the
fuel behaviour codes in use at VTT have been continued
topically, with attention to the most timely
requirements. The main achievements include: (1)
Development of a probabilistic procedure applicable for
general transient conditions, or for evaluation of the
number of failed rods in an accident, particularly, was
completed by a suggested two-stage approach one of which
features an innovative use of neural networks
methodology. (2) Use of the coupled thermal-hydraulic
fuel code FRAPTRAN-GENFLO was established as a versatile
tool to simulate integral loss-of-coolant test
arrangements and as the core tool in the probabilistic
transient analyses. (3) An extensive study on the
VTT-amended ENIGMA steady-state code and its several
sub-models was compiled. (4) A comprehensive
interpretation of the outcome of the in-pile measurements
from the OECD Halden Project rod overpressure tests was
issued. (5) A coupling to the ENIGMA code input from a
lattice physics code was created to realistically account
for the effect of gadolinium or other additives on power
distribution in the pellet. (6) Recent versions of the
IRSN SCANAIR code for reactivity accident analyses have
been installed and applied in power reactor applications.
(7) Two new versions of the USNRC FRAPCON and FRAPTRAN
codes were assembled. A version of FRAPCON 3.4
consolidating previous practical amendments and cleared
of intractable parts of obsolete coding was issued. (8)
Part was taken in three systematic international
benchmark exercises that effectively support the code
validation.
AB - Assessment, validation, and further development of the
fuel behaviour codes in use at VTT have been continued
topically, with attention to the most timely
requirements. The main achievements include: (1)
Development of a probabilistic procedure applicable for
general transient conditions, or for evaluation of the
number of failed rods in an accident, particularly, was
completed by a suggested two-stage approach one of which
features an innovative use of neural networks
methodology. (2) Use of the coupled thermal-hydraulic
fuel code FRAPTRAN-GENFLO was established as a versatile
tool to simulate integral loss-of-coolant test
arrangements and as the core tool in the probabilistic
transient analyses. (3) An extensive study on the
VTT-amended ENIGMA steady-state code and its several
sub-models was compiled. (4) A comprehensive
interpretation of the outcome of the in-pile measurements
from the OECD Halden Project rod overpressure tests was
issued. (5) A coupling to the ENIGMA code input from a
lattice physics code was created to realistically account
for the effect of gadolinium or other additives on power
distribution in the pellet. (6) Recent versions of the
IRSN SCANAIR code for reactivity accident analyses have
been installed and applied in power reactor applications.
(7) Two new versions of the USNRC FRAPCON and FRAPTRAN
codes were assembled. A version of FRAPCON 3.4
consolidating previous practical amendments and cleared
of intractable parts of obsolete coding was issued. (8)
Part was taken in three systematic international
benchmark exercises that effectively support the code
validation.
M3 - Chapter or book article
SN - 978-951-38-7689-0
T3 - VTT Tiedotteita - Research Notes
SP - 118
EP - 131
BT - SAFIR2010
PB - VTT Technical Research Centre of Finland
CY - Espoo
ER -