TY - CHAP
T1 - Transient behaviour of high burnup fuel (KOTO)
T2 - KOTO summary report
AU - Kelppe, Seppo
PY - 2002
Y1 - 2002
N2 - There is a clear economic incentive for the industry to continue the
trend of pursuing higher fuel discharge burnups, which translates into higher
neutron fluences, often together with longer residence times in the
reactor. Testing and irradiation experience demonstrates that it is feasible
in terms of reliability and safety to operate fuel beyond the recent burnup
limits in normal conditions. Still until now, the acceptance criteria for
transient and accident conditions have broadly based on early data that are
often from much lower burnups, and high burnup effects must not be overlooked
as regards postulated accident behaviour. The project supports assessing the
licensing criteria and evaluating the consequences of efforts for improved
fuel utilisation. Statistical methods for fuel analyses have been elaborated
for extensive applications. A new development featuring advanced thermal
hydraulics coupled with a fuel accident performance model, the
FRAPTRAN-GENFLO code, is opening an unparalleled capability for realistic
transient simulation. Well-placed international participation is providing
data from representative test conditions and burnup ranges relevant to model
development and validation for the near future. During the project period,
the Finnish nuclear utilities were granted a discharge burnup limit extension
from 40 to 45 MWd/kgU in assembly average for the fuel types in use.
AB - There is a clear economic incentive for the industry to continue the
trend of pursuing higher fuel discharge burnups, which translates into higher
neutron fluences, often together with longer residence times in the
reactor. Testing and irradiation experience demonstrates that it is feasible
in terms of reliability and safety to operate fuel beyond the recent burnup
limits in normal conditions. Still until now, the acceptance criteria for
transient and accident conditions have broadly based on early data that are
often from much lower burnups, and high burnup effects must not be overlooked
as regards postulated accident behaviour. The project supports assessing the
licensing criteria and evaluating the consequences of efforts for improved
fuel utilisation. Statistical methods for fuel analyses have been elaborated
for extensive applications. A new development featuring advanced thermal
hydraulics coupled with a fuel accident performance model, the
FRAPTRAN-GENFLO code, is opening an unparalleled capability for realistic
transient simulation. Well-placed international participation is providing
data from representative test conditions and burnup ranges relevant to model
development and validation for the near future. During the project period,
the Finnish nuclear utilities were granted a discharge burnup limit extension
from 40 to 45 MWd/kgU in assembly average for the fuel types in use.
M3 - Chapter or book article
SN - 951-38-6085-X
T3 - VTT Tiedotteita - Research Notes
SP - 95
EP - 103
BT - FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002
PB - VTT Technical Research Centre of Finland
CY - Espoo
ER -