Study of online measurements techniques of metallic phase spatial distribution into a corium pool

Autor: Tisseur D., Cavaro M., Rey F., Paumel K., Chikhi N., Delacroix J., Fouquart P., Le Tellier R., Bouyer V.

Publikováno v: EPJ Web of Conferences, Vol 225, p 08003 (2020)

In the context of in-vessel retention (IVR) strategy in order to better assess the risk of reactor vessel failure, the knowledge related to the kinetics of immiscible liquid phases stratification phenomenon needs to be further improved. So far, only

Externí odkaz: https://doaj.org/article/e5c70dc9f77a445da4b26b97eba0c804

Fast high-energy X-ray imaging for Severe Accidents experiments on the future PLINIUS-2 platform

Autor: Berge L., Estre N., Tisseur D., Payan E., Eck D., Bouyer V., Cassiaut-Louis N., Journeau C., Tellier R.Le, Pluyette E.

Publikováno v: EPJ Web of Conferences, Vol 170, p 08003 (2018)

The future PLINIUS-2 platform of CEA Cadarache will be dedicated to the study of corium interactions in severe nuclear accidents, and will host innovative large-scale experiments. The Nuclear Measurement Laboratory of CEA Cadarache is in charge of re

Externí odkaz: https://doaj.org/article/50aeb42c360f44349e3c7cb7949c2197

Remote monitoring of Molten Core-Concrete Interaction experiment with Optical Fibre Sensors & perspectives to improve nuclear safety – DISCOMS project.

Autor: Lyoussi, A., Giot, M., Carette, M., Jenčič, I., Reynard-Carette, C., Vermeeren, L., Snoj, L., Le Dû, P., Maurin, L., Ferdinand, P., Bouyer, V., Denoix, A., Jouvin, G., Rougeault, S., Journeau, C., Molina, D., Tena, P., Ouerdane, Y.

Publikováno v: EPJ Web of Conferences; 1/1/2020, Vol. 225, p1-8, 8p

Molten Core Concrete Interaction Test in VULCANO Facility Preventing Initial Interfacial Crusts

Autor: Bouyer, V., Denoix, A., Christophe Journeau, Molina, D., Piluso, P., F Haquet, J., Foit, J., Fluhrer, B., Miassoedov, A.

Publikováno v: HAL
NUTHOS12-12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety
NUTHOS12-12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety, Oct 2018, Qingdao, China

International audience; In the frame of the Severe Accident Facilities for European Safety Targets (SAFEST) project,Karlsruhe Institute of Technology (KIT) and the Society for installation and Reactor Safety (GRS)have proposed to realize a Molten Cor

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::f93d03bfc2be650dbd492da865e0d8dc
https://hal-cea.archives-ouvertes.fr/cea-02338562

Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.