The QUENCH-15 experiment investigated the effect of ZIRLO™ cladding material on bundle oxidation and core reflood from maximum bundle temperature of 2150 K. The molten cladding metal at the hottest elevation was localized between outer and inner oxide layers. The analyses of the QUENCH-15 test data indicate a similar global bundle behavior as of bundle experiments QUENCH-14 (M5® claddings) and QUENCH-06 (Zircaloy-4 claddings)
Experiment QUENCH-20 with BWR geometry simulation bundle was conducted at KIT on 9th October 2019 in...
24 heated rods (internal tungsten heaters between 0 and 1024 mm, cladding oxidised region between-47...
Nine separate-effects tests with VVER fuel rod simulators (Zr-1Nb cladding, 150 mm length) on the co...
The QUENCH-19 test objective was the comparison of FeCrAl(Y) and ZIRLO™ claddings under similar elec...
In all severe accidents scenarios the main goal of operator actions (AMM, accident management measur...
The QUENCH experiments are to investigate the hydrogen release resulting from the water injection in...
The objective of the QUENCH experimental program at the Karlsruhe Research Center is to investigate ...
The QUENCH experiments are to investigate the hydrogen source term that results from the water injec...
The QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
The QUENCH experiments are to investigate the hydrogen source term that results from the water or st...
The main objective of the QUENCH program at KIT is the investigation of the hydrogen source term and...
The QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
A series of separate-effects tests is being carried out on Zircaloy PWR fuel rod cladding to study t...
the hydrogen source term that results from quenching an uncovered core, to examine the physico-chemi...
The QUENCH out-of-pile experiments are part of the Severe Fuel Damage (SFD) program at the Karlsruhe...
Experiment QUENCH-20 with BWR geometry simulation bundle was conducted at KIT on 9th October 2019 in...
24 heated rods (internal tungsten heaters between 0 and 1024 mm, cladding oxidised region between-47...
Nine separate-effects tests with VVER fuel rod simulators (Zr-1Nb cladding, 150 mm length) on the co...
The QUENCH-19 test objective was the comparison of FeCrAl(Y) and ZIRLO™ claddings under similar elec...
In all severe accidents scenarios the main goal of operator actions (AMM, accident management measur...
The QUENCH experiments are to investigate the hydrogen release resulting from the water injection in...
The objective of the QUENCH experimental program at the Karlsruhe Research Center is to investigate ...
The QUENCH experiments are to investigate the hydrogen source term that results from the water injec...
The QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
The QUENCH experiments are to investigate the hydrogen source term that results from the water or st...
The main objective of the QUENCH program at KIT is the investigation of the hydrogen source term and...
The QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
A series of separate-effects tests is being carried out on Zircaloy PWR fuel rod cladding to study t...
the hydrogen source term that results from quenching an uncovered core, to examine the physico-chemi...
The QUENCH out-of-pile experiments are part of the Severe Fuel Damage (SFD) program at the Karlsruhe...
Experiment QUENCH-20 with BWR geometry simulation bundle was conducted at KIT on 9th October 2019 in...
24 heated rods (internal tungsten heaters between 0 and 1024 mm, cladding oxidised region between-47...
Nine separate-effects tests with VVER fuel rod simulators (Zr-1Nb cladding, 150 mm length) on the co...