Zobrazeno 1 - 10
of 39
pro vyhledávání: '"Malouch, Fadhel"'
Autor:
Rochman Dimitri, Algora Alejandro, Àlvarez-Velarde Francisco, Bardelay Aurélie, Bremnes Øystein, Cabellos Oscar, Cano-Ott Daniel, Capponi Luigi, Carmouze Coralie, Caruso Stefano, Cummings Andrew, Dagan Ron, Fallot Muriel, Fiorito Luca, Giot Lydie, Govers Kevin, Häkkinen Silja, Hannstein Volker, Hoefer Axel, Huynh Tan Dat, Ichou Raphaëlle, Ilas Germina, Juutilainen Pauli, Koszuk Lukasz, Kromar Marjan, Lahaye Sébastien, Lam James, Laugier Frédéric, Launay Agnés, Léger Vincent, Lecarpentier David, Leppanen Jaakko, Malouch Fadhel, Martin Julie-Fiona, McGinnes David, Mills Robert William, Minato Futoshi, Nauchi Yasushi, Ortego Pedro, Petkov Plamen, Romojaro Pablo, Sato Shunsuke, Seidl Marcus, Shama Ahmed, Simeonov Teodosi, Sjöland Anders, Solans Virginie, Sommer Fabian, Tittelbach Sven, Tsilanizara Aimé, Vlassopoulos Efstathios, Vallet Vanessa, Vasiliev Alexander, Watanabe Tomoaki, Žerovnik Gašper
Publikováno v:
EPJ Nuclear Sciences & Technologies, Vol 10, p 9 (2024)
This paper summarized the efforts performed to understand decay heat estimation from existing spent nuclear fuel (SNF), under the auspices of the Working Party on Nuclear Criticality Safety (WPNCS) of the OECD Nuclear Energy Agency. Needs for precise
Externí odkaz:
https://doaj.org/article/2b742f7a478842a89d12e53316e0faa9
Autor:
Malouch, Fadhel.
Th. doct.--Sci. nucléaires--Paris--CNAM, 2003.
La p. de titre porte en plus : "Direction de l'énergie nucléaire" Bibliogr. p. 225-232. Résumé en français et en anglais.
La p. de titre porte en plus : "Direction de l'énergie nucléaire" Bibliogr. p. 225-232. Résumé en français et en anglais.
Externí odkaz:
http://catalogue.bnf.fr/ark:/12148/cb39101311h
Autor:
Coste-Delclaux Mireille, Jouanne Cédric, Moreau Frédéric, Mounier Claude, Visonneau Thierry, Malouch Fadhel
Publikováno v:
EPJ Web of Conferences, Vol 211, p 05001 (2019)
This paper describes the current status of GALILÉE-1 that is the new verification and processing system for evaluated data, developed at CEA. It consists of various components respectively dedicated to read/write the evaluated data whatever the form
Externí odkaz:
https://doaj.org/article/a84be4e205184e57b1c311de402c2d4a
Autor:
Malouch, Fadhel1, Brun, Emeric1, Diop, Cheikh1, Hugot, François-Xavier1, Jouanne, Cédric1, Lee, Yi-Kang1, Malvagi, Fausto1, Mancusi, Davide1, Mazzolo, Alain1, Petit, Odile1, Trama, Jean-Christophe1, Visonneau, Thierry1, Zoia, Andrea1
Publikováno v:
EPJ Web of Conferences. 2017, Vol. 153, p1-6. 6p.
Publikováno v:
EPJ Web of Conferences, Vol 170, p 01008 (2018)
TRIPOLI-4® is a Monte-Carlo particle-transport code developed at CEA-Saclay (France) that is employed in the domains of nuclear-reactor physics, criticality-safety, shielding/radiation protection and nuclear instrumentation. The goal of this paper i
Externí odkaz:
https://doaj.org/article/82977fe22ec74eddbabbd3bf8aeb471d
Autor:
Jaboulay Jean-Charles, Brun Emeric, Hugot François-Xavier, Huynh Tan-Dat, Malouch Fadhel, Mancusi Davide, Tsilanizara Aime
Publikováno v:
EPJ Web of Conferences, Vol 153, p 02008 (2017)
After fission or fusion reactor shutdown the activated structure emits decay photons. For maintenance operations the radiation dose map must be established in the reactor building. Several calculation schemes have been developed to calculate the shut
Externí odkaz:
https://doaj.org/article/edfa27ebd3c54058859750152ee67599
Publikováno v:
EPJ Web of Conferences, Vol 153, p 06028 (2017)
This paper presents an overview of NARMER-1, the new generation of photon point-kernel code developed by the Reactor Studies and Applied Mathematics Unit (SERMA) at CEA Saclay Center. After a short introduction giving some history points and the curr
Externí odkaz:
https://doaj.org/article/51747db2887648ce8f628fb361ba481a
Autor:
Penessot Gaël, Bavoil Éléonore, Wertz Laurent, Malouch Fadhel, Visonneau Thierry, Dubost Julien
Publikováno v:
EPJ Web of Conferences, Vol 153, p 05021 (2017)
PANTHERE is a multipurpose radiation protection software developed by EDF to calculate gamma dose rates in complex 3D environments. PANTHERE takes a key role in the EDF ALARA process, enabling to predict dose rates and to organize and optimize operat
Externí odkaz:
https://doaj.org/article/88b9d00eb58e445793cec7c0d29c7d92
Publikováno v:
EPJ Web of Conferences, Vol 106, p 05006 (2016)
In this paper we present a nuclear heating from neutron and photon rays calculation scheme mainly based on the Monte-Carlo neutral particle transport code TRIPOLI-4® which takes into account the axial distributions of fuel element compositions. This
Externí odkaz:
https://doaj.org/article/9b4f43c0702b4d86b54531937a5d8e2e
Autor:
Malouch Fadhel
Publikováno v:
EPJ Web of Conferences, Vol 106, p 02012 (2016)
An irradiation program DV50 was carried out from 2002 to 2006 in the OSIRIS material testing reactor (CEA-Saclay center) to assess the pressure vessel steel toughness curve for a fast neutron fluence (E > 1 MeV) equivalent to a French 900-MWe PWR lif
Externí odkaz:
https://doaj.org/article/4d8b655d2050439c81a4def2e583bdb1