Similar Items: Behavior of a VVER fuel element tested under severe accident conditions in the CORA facility.
- Dry core BWR test CORA-33: test results.
- BWR slow heatup test CORA-31: test results.
- Proceedings of specialist meeting on the behaviour of water reactor fuel elements under accident conditions.
- Behavior of pre-irradiated fuel under a simulated ria condition [results of NSRR test JM-3].
- Behavior of pre-irradiated fuel under a simulated ria condition [results of NSRR test JM-4].
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Author: Hagen, S.
Author: Hofmann, P.
- Dry core BWR test CORA-33: test results.
- BWR slow heatup test CORA-31: test results.
- Chemical interactions between as-received and pre oxidized Zircaloy-4 and inconel-718 at high temperatures.
- Chemical interactions between as-received and pre oxidized Zircaloy-4 and stainless steel at high temperatures.
- Compatibility of graphite with a martensitic-ferritic steel, an austenitic stainless steel and a Ni-Base alloy up to 1250°C.
- Behavior of a VVER fuel element tested under severe accident conditions in the CORA facility.