On line neutron flux mapping in fuel coolant channels of a research reactor
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 |
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Přispěvatelé: | Département Etude des Réacteurs (DER), CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Australian Nuclear Science and Technology Organisation [Australie] (ANSTO), Laboratoire Capteurs et Architectures Electroniques (LCAE), Département Métrologie Instrumentation & Information (DM2I), Laboratoire d'Intégration des Systèmes et des Technologies (LIST), Direction de Recherche Technologique (CEA) (DRT (CEA)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Direction de Recherche Technologique (CEA) (DRT (CEA)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-Laboratoire d'Intégration des Systèmes et des Technologies (LIST), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay, Laboratoire d'Intégration des Systèmes et des Technologies (LIST (CEA)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-Laboratoire d'Intégration des Systèmes et des Technologies (LIST (CEA)) |
Rok vydání: | 2013 |
Předmět: |
Nuclear and High Energy Physics
neutron flux Materials science Nuclear engineering Astrophysics::High Energy Astrophysical Phenomena Assembly Nuclear Theory Radiation effects Fuels [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex] 7. Clean energy 01 natural sciences 010305 fluids & plasmas fission research reactors neutronic calculations 030218 nuclear medicine & medical imaging 03 medical and health sciences 0302 clinical medicine Neutron flux on-line neutron flux mapping 0103 physical sciences Neutron cross section Inductors Neutron detection fission reactor cooling Neutron Research reactor Electrical and Electronic Engineering Nuclear Experiment Neutrons fission chamber Coolants 010308 nuclear & particles physics Detectors fuel coolant channels [INFO.INFO-MO]Computer Science [cs]/Modeling and Simulation Neutron temperature Coolant Campbell mode Radiation flux OPAL research reactor Nuclear Energy and Engineering research reactor subminiature fission chambers on line neutron flux mapping [PHYS.PHYS.PHYS-DATA-AN]Physics [physics]/Physics [physics]/Data Analysis Statistics and Probability [physics.data-an] |
Zdroj: | 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⟩ |
ISSN: | 0018-9499 |
DOI: | 10.1109/animma.2013.6727951 |
Popis: | 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 mapping of the OPAL research reactor. A specific irradiation device has been set up to investigate fuel coolant channels using subminiature fission chambers to get thermal neutron flux profiles. Experimental results are compared to first neutronic calculations and show good agreement (C/E ∼0.97). |
Databáze: | OpenAIRE |
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