SEFLEX - fuel rod simulator effects in flooding experiments, Pt. 2.. Unblocked bundle data
- Location
-
Deutsche Nationalbibliothek Frankfurt am Main
- Extent
-
III, 200 S.
- Language
-
Englisch
- Notes
-
171 graph. Darst.
- Bibliographic citation
-
SEFLEX - fuel rod simulator effects in flooding experiments
- Event
-
Veröffentlichung
- (where)
-
Karlsruhe
- (who)
-
Kernforschungszentrum
- (when)
-
1986
- Table of contents
- Rights
-
Bei diesem Objekt liegt nur das Inhaltsverzeichnis digital vor. Der Zugriff darauf ist unbeschränkt möglich.
- Last update
-
11.03.2025, 12:34 PM CET
Data provider
This object is provided by:
Deutsche Nationalbibliothek. If you have any questions about the object, please contact the data provider.
Deutsche Nationalbibliothek. If you have any questions about the object, please contact the data provider.
Associated
- Kernforschungszentrum
Time of origin
- 1986
Other Objects (12)
SEFLEX - fuel rod simulator effects in flooding experiments, Pt. 3.. Blocked bundle data
SEFLEX - fuel rod simulator effects in flooding experiments, Pt. 1.. Evaluation report
Investigation of an overheated PWR-Type fuel rod simulator bundle cooled down by steam
Posttest examination fo the VVER-1000 fuel rod bundle CORA-W2
Temperature escalation in PWR fuel rod simulator bundles due to the zircaloy steam reaction, [...]. Post test investigations of bundle test ESBU-2A
Post test investigation of the bundle test ESBU-1 : on temperature escalation in PWR fuel rod simulator bundles due to the zirkaloy/steam reaction
Simulator Effects in Flooding Experiments (SEFLEX)-Anlage am Institut für Reaktorbauelemente (IRB)
Benchmark thermal-hydraulic analysis with the agathe hex 37-rod bundle
Temperature escalation in PWR fuel rod simulator bundles due to the zircaloy steam reaction, [...]. Test ESBU-1 : test results report
Temperature escalation in PWR fuel rod simulator bundles due to the zircaloy steam reaction, [...]. Test ESBU-2A : test results report
Versuchsstand Heated Rod Bundle Assembly (HERA) des Instituts für Nukleare Entsorgungstechnik (INE)
Behavior of AgInCd absorber material in Zry UO2 fuel rod simulator bundles tested at high temperatures in the CORA facility
SEFLEX - fuel rod simulator effects in flooding experiments, Pt. 3.. Blocked bundle data
SEFLEX - fuel rod simulator effects in flooding experiments, Pt. 1.. Evaluation report
Investigation of an overheated PWR-Type fuel rod simulator bundle cooled down by steam
Posttest examination fo the VVER-1000 fuel rod bundle CORA-W2
Temperature escalation in PWR fuel rod simulator bundles due to the zircaloy steam reaction, [...]. Post test investigations of bundle test ESBU-2A
Post test investigation of the bundle test ESBU-1 : on temperature escalation in PWR fuel rod simulator bundles due to the zirkaloy/steam reaction
Simulator Effects in Flooding Experiments (SEFLEX)-Anlage am Institut für Reaktorbauelemente (IRB)
Benchmark thermal-hydraulic analysis with the agathe hex 37-rod bundle
Temperature escalation in PWR fuel rod simulator bundles due to the zircaloy steam reaction, [...]. Test ESBU-1 : test results report
Temperature escalation in PWR fuel rod simulator bundles due to the zircaloy steam reaction, [...]. Test ESBU-2A : test results report
Versuchsstand Heated Rod Bundle Assembly (HERA) des Instituts für Nukleare Entsorgungstechnik (INE)
Behavior of AgInCd absorber material in Zry UO2 fuel rod simulator bundles tested at high temperatures in the CORA facility
SEFLEX - fuel rod simulator effects in flooding experiments, Pt. 3.. Blocked bundle data
SEFLEX - fuel rod simulator effects in flooding experiments, Pt. 1.. Evaluation report
Investigation of an overheated PWR-Type fuel rod simulator bundle cooled down by steam
Posttest examination fo the VVER-1000 fuel rod bundle CORA-W2
Temperature escalation in PWR fuel rod simulator bundles due to the zircaloy steam reaction, [...]. Post test investigations of bundle test ESBU-2A
Post test investigation of the bundle test ESBU-1 : on temperature escalation in PWR fuel rod simulator bundles due to the zirkaloy/steam reaction
Simulator Effects in Flooding Experiments (SEFLEX)-Anlage am Institut für Reaktorbauelemente (IRB)
Benchmark thermal-hydraulic analysis with the agathe hex 37-rod bundle
Temperature escalation in PWR fuel rod simulator bundles due to the zircaloy steam reaction, [...]. Test ESBU-1 : test results report
Temperature escalation in PWR fuel rod simulator bundles due to the zircaloy steam reaction, [...]. Test ESBU-2A : test results report
Versuchsstand Heated Rod Bundle Assembly (HERA) des Instituts für Nukleare Entsorgungstechnik (INE)