The QUENCH-LOCA-5 test with pre-hydrogenated optimised ZIRLO™ claddings (≈300 wppm H) was performed according to a temperature/time-scenario typical for a LBLOCA in a German PWR with the similar parameters as the QUENCH-LOCA-3 test with fresh optimised ZIRLO™ claddings: maximal heat-up rate 8 K/s, cooling phase lasted 120 s and terminated with 3.3 g/s/rod water flooding. Significant difference was the lower temperature before the start of the transient (to decrease the dissolution of hydrides during the conditioning stage of experiment). Accordingly to this, the lower maximum temperature of 1250 K was reached on the end of the heat-up phase at elevation 950 mm (1350 K for QUENCH-LOCA-3). Tangential temperature gradient across a rod was up t...
The QUENCH-14 experiment investigated the effect of M5 ® cladding material on bundle oxidation and c...
The QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
Department of Nuclear EngineeringThe possibility of breakaway oxidation of zirconium alloy cladding ...
Seven QUENCH-LOCA bundle tests (QUENCH-L0…-L5 and -L3HT) with different cladding materials (Zry-4, M...
The QUENCH-19 bundle experiment with FeCrAl(Y) claddings and 4 FeCrAl(Y) spacer grids as well as 8 K...
The QUENCH-19 test objective was the comparison of FeCrAl(Y) and ZIRLO™ claddings under similar elec...
24 heated rods (internal tungsten heaters between 0 and 1024 mm, cladding oxidised region between-47...
The experiment QUENCH-20 with BWR geometry simulation bundle was successfully conducted at KIT on 9t...
Experiment QUENCH-20 with BWR geometry simulation bundle was conducted at KIT on 9th October 2019 in...
The QUENCH-15 experiment investigated the effect of ZIRLO™ cladding material on bundle oxidati...
In the framework of the SARNET-2 European program the QUENCH-DEBRIS test was conducted as the 17th s...
The main objective of the QUENCH program at KIT is the investigation of the hydrogen source term and...
the hydrogen source term that results from quenching an uncovered core, to examine the physico-chemi...
Quenching phenomenon is one of the most unexplored phenomena in the field of heat transfer. However,...
Experiment QUENCH-20 with BWR geometry simulation bundle was successfully conducted at KIT on 9th Oc...
The QUENCH-14 experiment investigated the effect of M5 ® cladding material on bundle oxidation and c...
The QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
Department of Nuclear EngineeringThe possibility of breakaway oxidation of zirconium alloy cladding ...
Seven QUENCH-LOCA bundle tests (QUENCH-L0…-L5 and -L3HT) with different cladding materials (Zry-4, M...
The QUENCH-19 bundle experiment with FeCrAl(Y) claddings and 4 FeCrAl(Y) spacer grids as well as 8 K...
The QUENCH-19 test objective was the comparison of FeCrAl(Y) and ZIRLO™ claddings under similar elec...
24 heated rods (internal tungsten heaters between 0 and 1024 mm, cladding oxidised region between-47...
The experiment QUENCH-20 with BWR geometry simulation bundle was successfully conducted at KIT on 9t...
Experiment QUENCH-20 with BWR geometry simulation bundle was conducted at KIT on 9th October 2019 in...
The QUENCH-15 experiment investigated the effect of ZIRLO™ cladding material on bundle oxidati...
In the framework of the SARNET-2 European program the QUENCH-DEBRIS test was conducted as the 17th s...
The main objective of the QUENCH program at KIT is the investigation of the hydrogen source term and...
the hydrogen source term that results from quenching an uncovered core, to examine the physico-chemi...
Quenching phenomenon is one of the most unexplored phenomena in the field of heat transfer. However,...
Experiment QUENCH-20 with BWR geometry simulation bundle was successfully conducted at KIT on 9th Oc...
The QUENCH-14 experiment investigated the effect of M5 ® cladding material on bundle oxidation and c...
The QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
Department of Nuclear EngineeringThe possibility of breakaway oxidation of zirconium alloy cladding ...