Developments and needs in nuclear analysis of fusion technology |
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Authors: | R Pampin A Davis J Izquierdo D Leichtle MJ Loughlin J Sanz A Turner R Villari PPH Wilson |
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Affiliation: | 1. CCFE, Culham Science Centre, Abingdon OX14 3DB, United Kingdom;2. F4E Fusion For Energy, Josep Pla 2, Torres Diagonal Litoral B3, Barcelona 08019, Spain;3. Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz Platz 1, D-76344 Karlsruhe, Germany;4. ITER Organisation, Route de Vinon sur Verdon, 13115 Saint Paul lez Durance, France;5. UNED, Departamento de Ingenieria Energetica, Juan del Rosal 12, 28040 Madrid, Spain;6. Associazione EURATOM-ENEA sulla Fusione, Via Enrico Fermi 45, 00044 Frascati, Rome, Italy;7. University of Wisconsin, Nuclear Engineering Department, Madison, WI, USA |
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Abstract: | Nuclear analyses provide essential input to the conceptual design, optimisation, engineering and safety case of fusion technology in current experiments, ITER, next-step devices and power plant studies. Calculations are intricate and computer-intensive, typically requiring detailed geometry models, sophisticated acceleration algorithms, high-performance parallel computations, and coupling of large and complex transport and activation codes and databases. This paper reports progress on some key areas in the development of tools and methods to meet the specific needs of fusion nuclear analyses. In particular, advances in the production and modernisation of reference models, in the preparation and quality assurance of acceleration algorithms and coupling schemes, and in the evaluation and adaptation of alternative transport codes are presented. Emphasis is given to ITER-relevant activities, which are the main driver of advances in the field. Discussion is made of the importance of efforts in these and other areas, considering some of the more pressing needs and requirements. In some cases, they call for a more efficient and coordinated use of the scarce resources available. |
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Keywords: | Nuclear analysis Neutronics Activation Shielding ITER |
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