Zobrazeno 1 - 10
of 18
pro vyhledávání: '"SONNENKALB, Martin"'
Autor:
Freitag, Martin, Schmidt, Eike W., Sonnenkalb, Martin, Kelm, Stephan, Kotouč, Miroslav, Liang, Zhe, Royl, Peter, Benz, Stefan
Publikováno v:
In Nuclear Engineering and Design 15 December 2022 400
Publikováno v:
In Nuclear Engineering and Design June 2014 272:183-194
Autor:
Wielenberg, Andreas, Beck, Sara, Hollands, Thorsten, Lovasz, Liviusz, Nowack, Holger, Spengler, Claus, Sonnenkalb, Martin, Schaffrath, Andreas
Publikováno v:
In Nuclear Power Plant Design and Analysis Codes 2021:363-395
Autor:
CENERINO, Gerard, PIGNET, Sophie, VAN ROMPUY, Thibaut, MAZZINI, Guido, MASCARI, Fulvio, SONNENKALB, Martin, CONSTANTIN, Marin, KLJENAK, Ivo, URBONAVICIUS, Egidijus, LIND, Terttaliisa, JANCOVIC, Juraj, LINDHOLM, Ilona
Publikováno v:
International Seminar “In-vessel retention: outcomes of IVMR project”, IVMR
International Seminar “In-vessel retention: outcomes of IVMR project”, IVMR, 2020, JUAN LES PINS, France
International Seminar “In-vessel retention: outcomes of IVMR project”, IVMR, 2020, JUAN LES PINS, France
International audience; In-Vessel melt Retention (IVR) is a Severe Accident (SA) mitigation measure applied in some Pressurized Water Reactors (PWRs) in order to cool down molten fuel (corium) inside the Reactor Pressure Vessel (RPV) by flooding the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::b044337a8d318b9319e5ecafa7f1a57d
https://hal.archives-ouvertes.fr/hal-03150524/file/0000163853_003.PDF
https://hal.archives-ouvertes.fr/hal-03150524/file/0000163853_003.PDF
Autor:
Lind, Terttaliisa, Pellegrini, Marco, Herranz, Luis Enrique, Sonnenkalb, Martin, Nishi, Y., Tamaki, H., Cousin, F., Fernandez-Moguel, Leticia, Andrews, Nathan, Sevon, Tuomo
Publikováno v:
Lind, T, Pellegrini, M, Herranz, L E, Sonnenkalb, M, Nishi, Y, Tamaki, H, Cousin, F, Fernandez-Moguel, L, Andrews, N & Sevon, T 2019, Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi NPS (BSAF) Phase 2 : Results of Severe Accident Analyses for Unit 3 . in Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-18 . American Nuclear Society (ANS), pp. 1133-1146, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, Portland, Oregon, United States, 18/08/19 .
The Phase 2 of the OECD/NEA Project “Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF)” was established in mid-2015. The objectives were similar to Phase 1 of the project but with an extended analysis period of 3
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::ff7650467117668419c3fe06918dfaba
https://cris.vtt.fi/en/publications/79eeda93-7a88-4e0c-b2da-b492664c125c
https://cris.vtt.fi/en/publications/79eeda93-7a88-4e0c-b2da-b492664c125c
Autor:
Adorni, M., Bals, Christine, Beck, Sara, Bernaud, S., Boulore, A., Chauvin, N., Cheng, Hui, Dailey, Ryan, Del Nevo, A., Dong, Xiaomeng, Duan, Guangtao, Dumas, J.C., Duncan, A., Feng, Tangtao, Gui, Miao, Gurgen, Anil, Helfer, T., Hollands, Thorsten, Introini, C., Koshizuka, Seiichi, Lainet, M., Li, Xin, Lin, Lianshan, Lovasz, Liviusz, Luzzi, L., Magni, A., Marelle, V., Masson, R., Michel, B., Mondry, Kaya G., Ni, Xinghe, Noirot, L., Nowack, Holger, Pellegrini, Marco, Perez, Alejandro, Qiu, Bowen, Ramière, I., Rozzia, D., Saito, Shimpei, Schaffrath, Andreas, Schubert, A., Sercombe, J., Sonnenkalb, Martin, Spengler, Claus, Su, Guanghui, Sun, Lin, Sun, Z.J., Van Uffelen, P., Vayssier, George, Viallard, I., Wang, Jun, Wang, Xing, Wang, Zidi, Wielenberg, Andreas, Xi, Jianqi, Yamaji, Akifumi, Yu, Jiankai, Zhang, Fan, Zhang, Jing, Zhang, Luteng, Zhang, Tengfei, Zhao, Xingang, Zhong, Xianping, Zhou, Yukun
Publikováno v:
In Nuclear Power Plant Design and Analysis Codes 2021:ix-xi
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.
Autor:
Bonelli, Analia, Mazzantini, Oscar, Sonnenkalb, Martin, Caputo, Marcelo, García, Juan Matias, Zanocco, Pablo, Gimenez, Marcelo
Publikováno v:
Science and Technology of Nuclear Installations.
A description of the results for a Station Black-Out analysis for Atucha 2 Nuclear Power Plant is presented here. Calculations were performed with MELCOR 1.8.6 YV3165 Code. Atucha 2 is a pressurized heavy water reactor, cooled and moderated with heav
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=hindawi_publ::640fb5e835d0f4b3c03acf31ab5e112e
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.