Modelling effects on axial neutron flux in a Tokamak device |
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| Affiliation: | 1. Departamento de Engenharia Nuclear (DEN) – Escola de Engenharia, Universidade Federal de Minas Gerais (UFMG), Av. Antônio Carlos, 6627, 31270-901 Campus Pampulha, Belo Horizonte, MG, Brazil;2. Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, Brazil;3. Rede Nacional de Fusão (FINEP/CNPq), Brazil;1. Key Laboratory of Materials Modification by Laser, Ion and Electron Beams (Ministry of Education), School of Physics and Optoelectronic Technology, Dalian University of Technology, Dalian 116024, China;2. School of Information Science and Engineering, Dalian Polytechnic University, Dalian 116034, China;1. International Fusion Energy Research Centre (IFERC), Japan;2. Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia-BarcelonaTech, Spain;3. Japan Atomic Energy Agency (JAEA), Japan;1. Kyung Hee University, Youngin-si, Gyeonggi-do 446-701, Republic of Korea;2. Pakistan Institute of Engineering and Applied Sciences, Nilore, Pakistan;3. Korea Atomic Energy Institute, Daejeon-si 305-353, Republic of Korea;1. UKAEA-CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB, UK;2. IRFM CEA Cadarache, 13108 Saint Paul lez Durance, France;3. Institute of Plasma Physics of the CAS, 18200 Prague, Czechia;4. EUROfusion – Programme Management Unit, Boltzmannstrasse 2, 85748 Garching, Germany;1. JET-EFDA, Culham Science Centre, Abingdon OX14 3 DB, UK;2. Institute of Plasma Physics AS CR, Association EURATOM-IPP.CR, 182 00 Praha 8, Czech Republic;3. Aalto University, Association EURATOM-Tekes, Espoo, Finland;4. CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France;5. ITER Organization, Route de Vinon-sur-Verdon, CS 90 04, 613067 St. Paul Lez Durance Cedex, France;6. Association EURATOM-ÖAW, Institute of Applied Physics, TU Wien, A-6020 Vienna, Austria |
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| Abstract: | Using Monte Carlo N-Particle (MCNP5), three different Tokamak models using different geometries were simulated, maintaining some basic parameters from the ITER design. The neutron flux and the reaction rates were obtained over different volumes: FW, divertor and along the different device walls. The three geometries were compared under the same conditions. The results showed the behaviour of the neutron flux spectra along the different walls, as well as, the most suitable model taking in consideration the different analyses and the final purpose of adding a transmutation layer. Finally, the chosen geometry will be used to analyse the burnup, buildup, decay, and processing of material under irradiation. |
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| Keywords: | Neutron flux MCNP Tokamak |
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