Zobrazeno 1 - 9
of 9
pro vyhledávání: '"George Braoudakis"'
Autor:
Robert Raposio, George Braoudakis, Anatoly Rosenfeld, Gordon Thorogood, Juniper Bedwell-Wilson
Publikováno v:
Frontiers in Nuclear Engineering. 1
Introduction: Current fission-based methods of 99Mo production use targets that are based on high output without taking into consideration the amount of radioactive waste produced. We examine the idea of using a low enriched target (99Mo via fission
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d6885a3b70f5a81ebf30ff63cd0fdee1
https://doi.org/10.3389/fnuen.2022.978948
https://doi.org/10.3389/fnuen.2022.978948
Publikováno v:
Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine. 176
Current fission-based methods of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=pmid________::6dc2051a54c57b5f60e332ecedc1bf8f
https://pubmed.ncbi.nlm.nih.gov/34144410
https://pubmed.ncbi.nlm.nih.gov/34144410
Publikováno v:
Applied Radiation and Isotopes. 176:109827
Current fission-based methods of 99Mo production require single use uranium targets which leads to spent uranium waste. This waste could be reduced if a target is developed that does not require dissolution so that it can be reused for multiple produ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d860f798ad2fab9085ed873164e6fbd1
https://doi.org/10.1016/j.apradiso.2021.109827
https://doi.org/10.1016/j.apradiso.2021.109827
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, 2017, 110, pp.11-24. ⟨10.1016/j.anucene.2017.06.012⟩
Annals of Nuclear Energy, 2017, 110, pp.11-24. ⟨10.1016/j.anucene.2017.06.012⟩
International audience; We compute the dynamic reactivity of several reactor configurations by resorting to Monte Carlo simulation. The adjoint-weighted kinetics parameters are first determined by the Iterated Fission Probability (IFP) method, togeth
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8c97b15d97bdc9472834540e89984fba
https://doi.org/10.1016/j.anucene.2017.06.012
https://doi.org/10.1016/j.anucene.2017.06.012
Neutron-moderator scattering interactions in the thermal energy range are often treated with specialised cross section data derived from the Thermal Scattering Law S(α,β). This scattering law is calculated based on theoretical and experimental mode
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::92c4d290b08474a090998d56c0d81135
https://www.sciencedirect.com/science/article/pii/S0306454918303682
https://www.sciencedirect.com/science/article/pii/S0306454918303682
Publikováno v:
Physica B: Condensed Matter. :1321-1323
Monte Carlo simulations may be used to model radiation shielding for neutron diffractometers. The use of the MCNP computer program to assess shielding for a diffractometer is discussed. A comparison is made of shielding requirements for radiation gen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::260c1815e89ef26141129a388951d46d
https://doi.org/10.1016/j.physb.2006.06.064
https://doi.org/10.1016/j.physb.2006.06.064
Publikováno v:
Physica B: Condensed Matter. :1268-1270
Models of the neutron guide shielding for the out of bunker guides on the thermal and cold neutron beam lines of the OPAL Reactor (ANSTO) were constructed using the Monte Carlo code MCNP 4B. The neutrons that were not reflected inside the guides but
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::aa9be491028d39b837322f39b69cf047
https://doi.org/10.1016/j.physb.2006.06.028
https://doi.org/10.1016/j.physb.2006.06.028
Autor:
Christophe Blandin, John C. Osborn, Gwenolé Corre, Jean-Francois Villard, George Braoudakis, Loïc Barbot, Bradley Sinclair, Christophe Domergue, Stephane Normand, Mathieu Thevenin, David Wassink, Christophe Destouches, Huayou Wu
Publikováno v:
IEEE Transactions on Nuclear Science
IEEE Transactions on Nuclear Science, Institute of Electrical and Electronics Engineers, 2015, 62 (2), pp.415-419. ⟨10.1109/TNS.2015.2396637⟩
3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA)
3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA), Jun 2013, Marseille, France. ⟨10.1109/ANIMMA.2013.6727951⟩
IEEE Transactions on Nuclear Science, 2015, 62 (2), pp.415-419. ⟨10.1109/TNS.2015.2396637⟩
IEEE Transactions on Nuclear Science, Institute of Electrical and Electronics Engineers, 2015, 62 (2), pp.415-419. ⟨10.1109/TNS.2015.2396637⟩
3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA)
3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA), Jun 2013, Marseille, France. ⟨10.1109/ANIMMA.2013.6727951⟩
IEEE Transactions on Nuclear Science, 2015, 62 (2), pp.415-419. ⟨10.1109/TNS.2015.2396637⟩
Conference of 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications, ANIMMA 2013 ; Conference Code:102802; International audience; This work deals with the on-line neutron flux mappin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::52ed331790df488b8f9e71fa558dc0ca
https://doi.org/10.1109/animma.2013.6727951
https://doi.org/10.1109/animma.2013.6727951