Zobrazeno 1 - 10 of 12 pro vyhledávání: '"Fadhel Malouch"'
1
Advances in the Treatment of the Electromagnetic Cascade in the TRIPOLI-4 Monte Carlo Code
Autor: Davide Mancusi, F. X. Hugot, Fadhel Malouch, Alice Bonin
Publikováno v: IEEE Transactions on Nuclear Science. 65:2372-2379
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 is
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::97a208766673fc891ffb71f021cd2e79
https://doi.org/10.1109/tns.2018.2833287
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2
Recent developments in nuclear heating measurement methods inside the OSIRIS reactor
Autor: Hubert Carcreff, Laurent Salmon, Fadhel Malouch
Publikováno v: Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Elsevier, 2019, 942, pp.162310. ⟨10.1016/j.nima.2019.06.051⟩
Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2019, 942, pp.162310. ⟨10.1016/j.nima.2019.06.051⟩
Nuclear heating inside a Material Testing Reactor (MTR) needs to be known in order to design and to run irradiation experiments that have to fulfill target temperature constraints. To improve the incore nuclear heating knowledge of the French OSIRIS
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a01872f0ddb9e49f7f188abf41853066
https://hal-cea.archives-ouvertes.fr/cea-02535369
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3
Simulation and Comparison of the Calorimeters Measuring the Nuclear Heating in the OSIRIS Reactor, with the TRIPOLI-4 Monte-Carlo Code
Autor: A. Peron, Fadhel Malouch, C. M. Diop
Publikováno v: IEEE Transactions on Nuclear Science. 62:1218-1225
Two calorimeter devices are used in the OSIRIS Material Testing Reactor (CEA-Saclay center) for the nuclear heating measurements. The first one is a fixed five-stage calorimeter device. The second one is an innovative mobile probe called “CALMOS”
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::e58e7e9a6ba1a54774429ddf6ac664a6
https://doi.org/10.1109/tns.2015.2430616
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4
Methodological approach for DEMO neutronics in the European PPPT programme: Tools, data and analyses
Autor: J.-Ch. Jaboulay, Yuefeng Qiu, Fabio Moro, Rosaria Villari, Pavel Pereslavtsev, T. Eade, C. Bachmann, Dieter Leichtle, Gediminas Stankunas, Francisco Ogando, J.P. Catalan, Ulrich Fischer, Alexander Konobeev, Fadhel Malouch, Mark R. Gilbert, Anton Travleev, Davide Flammini, A. Turner, I. Palermo, Patrick Sauvan, Lei Lu, Javier Sanz
Publikováno v: Fusion engineering and design, 123, 26-31
Fusion Engineering and Design
The methodological approach employed for the neutronics in the PPPT (Power Plant Physics and Technology) programme of EUROfusion is presented. It encompasses development works on advanced computational tools and activities related to the nuclear desi
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2d9565648b760094f58c0c9ac8e957cb
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5
Panthere V2: Multipurpose Simulation Software for 3D Dose Rate Calculations
Autor: Thierry Visonneau, Fadhel Malouch, Laurent Wertz, Éléonore Bavoil, Gaël Penessot, Julien Dubost
Publikováno v: EPJ Web of Conferences, Vol 153, p 05021 (2017)
EPJ Web Conf.
13th International Conference on Radiation Shielding (ICRS-13) & 19th Topical Meeting of the Radiation Protection & Shielding Division of the American Nuclear Society-2016 (RPSD-2016)
13th International Conference on Radiation Shielding (ICRS-13) & 19th Topical Meeting of the Radiation Protection & Shielding Division of the American Nuclear Society-2016 (RPSD-2016), Oct 2016, Paris, France. pp.05021, ⟨10.1051/epjconf/201715305021⟩
International audience; 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 orga
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::188d013a7818f6fd7c1529aa08fa2459
https://doaj.org/article/88b9d00eb58e445793cec7c0d29c7d92
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6
Rigorous-two-Steps scheme of TRIPOLI-4® Monte Carlo code validation for shutdown dose rate calculation
Autor: Davide Mancusi, Emeric Brun, Jean-Charles Jaboulay, Aime Tsilanizara, F. X. Hugot, Fadhel Malouch, Tan-Dat Huynh
Publikováno v: EPJ Web Conf.
13th International Conference on Radiation Shielding (ICRS-13) & 19th Topical Meeting of the Radiation Protection & Shielding Division of the American Nuclear Society-2016 (RPSD-2016)
13th International Conference on Radiation Shielding (ICRS-13) & 19th Topical Meeting of the Radiation Protection & Shielding Division of the American Nuclear Society-2016 (RPSD-2016), Oct 2016, Paris, France. pp.02008, ⟨10.1051/epjconf/201715302008⟩
EPJ Web of Conferences, Vol 153, p 02008 (2017)
International audience; 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 develop
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b8abf9317126b854330629f6628c149f
https://hal.archives-ouvertes.fr/hal-01645299
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7
Recent developments in the TRIPOLI-4® Monte-Carlo code for shielding and radiation protection applications
Autor: Davide Mancusi, Fadhel Malouch, Alain Mazzolo, Thierry Visonneau, Cédric Jouanne, Yi-Kang Lee, Andrea Zoia, Cheikh Diop, F. X. Hugot, Fausto Malvagi, Jean-Christophe Trama, Odile Petit, Emeric Brun
Publikováno v: EPJ Web Conf.
13th International Conference on Radiation Shielding (ICRS-13) & 19th Topical Meeting of the Radiation Protection & Shielding Division of the American Nuclear Society-2016 (RPSD-2016)
13th International Conference on Radiation Shielding (ICRS-13) & 19th Topical Meeting of the Radiation Protection & Shielding Division of the American Nuclear Society-2016 (RPSD-2016), Oct 2016, Paris, France. pp.06007, ⟨10.1051/epjconf/201715306007⟩
EPJ Web of Conferences, Vol 153, p 06007 (2017)
International audience; TRIPOLI-4® is a 3D continuous-energy Monte-Carlo particle transport code developed by CEA (SERMA) and devoted to shielding, reactor physics, criticality-safety and nuclear instrumentation. In this paper, we present the recent
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::383206d799cc5f4786fb871d399cbc1a
https://hal.science/hal-01669771
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8
New Dosimetric Interpretation of the DV50 Vessel-Steel Experiment Irradiated in the OSIRIS MTR Reactor Using the Monte-Carlo Code TRIPOLI-4®
Autor: Fadhel Malouch
Publikováno v: EPJ Web of Conferences, Vol 106, p 02012 (2016)
ISRD 15-15th International Symposium on Reactor Dosimetry
ISRD 15-15th International Symposium on Reactor Dosimetry, May 2014, Aix en provence, France
International audience; 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>1MeV) equivalent to a F
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::fff0b7e5efbb610bef1c10c95531d81f
https://doaj.org/article/4d8b655d2050439c81a4def2e583bdb1
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9
Improvement of Nuclear Heating Evaluation Inside the Core of the OSIRIS Material Testing Reactor
Autor: Cheikh M. Diop, Arthur Péron, Fadhel Malouch
Publikováno v: EPJ Web of Conferences, Vol 106, p 05006 (2016)
ISRD 2014-15th International Symposium on Reactor Dosimetry
ISRD 2014-15th International Symposium on Reactor Dosimetry, May 2014, Aix en provence, France
International audience; 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 fuel elements axial distributions
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f971679957dfd2835ff41b4d1ee97968
https://doaj.org/article/9b4f43c0702b4d86b54531937a5d8e2e
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10
Advances in Monte-Carlo code TRIPOLI-4®’s treatment of the electromagnetic cascade
Autor: Alice Bonin, Davide Mancusi, F. X. Hugot, Fadhel Malouch
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://explore.openaire.eu/search/publication?articleId=doi_dedup___::cd5f3efcfe93d63d304b011c8a2c9241
https://doi.org/10.1051/epjconf/201817001008
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