Zobrazeno 1 - 10
of 101
pro vyhledávání: '"Trotignon, L."'
Autor:
Seiler, N., Bachrata, A., Bigot, B., Bouyer, V., Brayer, C., Charollais, F., Chauvin, R., Clavier, R., Denoix, A., Delacroix, J., Dufour, E., Francescatto, J., Gubernatis, P., Johnson, M., Journeau, C., Lecoanet, A., Le Tellier, R., Piluso, P., Pons, K., Saas, L., Trotignon, L.
Publikováno v:
In Nuclear Engineering and Design May 2024 421
Autor:
Benard, A., Rose, J., Hazemann, Jean-Louis, Proux, O., Trotignon, L., Borschneck, D., Nonat, A., Chateau, L., Bottero, J. -Y.
Publikováno v:
Advances in Cement Research 21, 1 (2009) 1-10
Complex cementitious matrices undergo weathering with environmental exchange and can release metallic pollutants during alteration. The molecular mechanisms responsible for metal release are difficult to identify, though this is necessary if such pro
Externí odkaz:
http://arxiv.org/abs/1402.2962
Publikováno v:
In Nuclear Engineering and Design May 2019 346:1-9
Publikováno v:
In Journal of Nuclear Materials September 2014 452(1-3):578-594
Publikováno v:
In Advances in Water Resources 2008 31(12):1540-1551
Publikováno v:
Internationnal Youth Nuclear Congress (IYNC-2020)
Internationnal Youth Nuclear Congress (IYNC-2020), Mar 2020, Sydney, Australia
Internationnal Youth Nuclear Congress (IYNC-2020), Mar 2020, Sydney, Australia
International audience; In the context of improved safety requirements for generation IV Sodium-cooled Fast Reactors (SFR), an innovative severe accident mitigation scenario is being investigated. The mitigation strategy consists of transfer tubes (D
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::baedad1adbe71ca3287dfa78b206f3b7
https://hal-cea.archives-ouvertes.fr/cea-02613584
https://hal-cea.archives-ouvertes.fr/cea-02613584
Degraded core relocation in Sodium-cooled Fast Reactor severe accident $-$ particle-size debris flow
Publikováno v:
IYNC 2020-International Youth Nuclear Congress
IYNC 2020-International Youth Nuclear Congress, Mar 2020, Sydney, Australia
IYNC 2020-International Youth Nuclear Congress, Mar 2020, Sydney, Australia
International audience; In the context of improved safety requirements for generation IV Sodium-cooled Fast Reactors (SFR), an innovative severe accident mitigation scenario is being investigated. The mitigation strategy consists of transfer tubes (D
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::82ac395c60546571a11f0db61e33e9e6
https://hal-cea.archives-ouvertes.fr/cea-02614131
https://hal-cea.archives-ouvertes.fr/cea-02614131
Publikováno v:
In Journal of Nuclear Materials 31 May 2007 362(2-3):493-501
Publikováno v:
In Physics and Chemistry of the Earth 2007 32(1):259-274
Publikováno v:
In Physics and Chemistry of the Earth 2006 31(10):618-625