Analysis of radiation environment at divertor in helical reactor FFHR-d1 |
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| Affiliation: | 1. Association KIT-Euratom, Karlsruhe Institute of Technology (KIT), Karlsruhe, Germany;2. European Fusion Development Agreement (EFDA), Garching, Germany;3. Association IPPLM-Euratom, IPPLM Warsaw/INP Krakow, Poland;4. Universidad Nacional de Educación a Distancia (UNED), Madrid, Spain;5. Fusion for Energy (F4E), Barcelona, Spain;6. MESCS-JSI, Ljubljana, Slovenia;7. CEA, DEN, Saclay, DM2S, SERMA, F-91191 Gif-sur-Yvette, France;8. Associazione ENEA-Euratom, ENEA Fusion Division, Frascati, Italy;9. Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (CIEMAT), Madrid, Spain;10. Budapest University of Technology and Economics (BME), Budapest, Hungary;11. Euratom/CCFE Fusion Association, Culham Science Centre for Fusion Energy (CCFE), Culham, UK;1. VTT Technical Research Centre of Finland, P.O. Box 1300, FI-33101 Tampere, Finland;2. Tampere University of Technology, Korkeakoulunkatu 6, 33720 Tampere, Finland;1. CIEMAT, Avda. Complutense 40, 28040 Madrid, Spain;2. IDOM, Avda. Monasterio de El Escorial 4, 28049 Madrid, Spain;1. Department of Energy System Engineering, Seoul National University, Seoul, Republic of Korea;2. Center for Advance Research in Fusion Reactor Engineering, Seoul National University, Seoul, Republic of Korea;3. ITER Korea, National Fusion Research Institute, Daejeon, Republic of Korea;4. ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul-lez-Durance, France;1. Karlsruhe Institute of Technology, 76344, Karlsruhe, Germany;2. EURATOM/CCFE Fusion Association, Culham Science Centre Abingdon, Oxfordshire OX14 3DB, UK |
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| Abstract: | Neutron transport calculations with a three-dimensional model of the helical reactor FFHR-d1 have been performed for the accurate analysis of neutronics environment in the divertor areas. Based on the obtained neutron spectra, magnitudes of irradiation damage, contact dose rates and decay heat have been evaluated mainly for Fe, W and Cu. Since divertors can be placed behind radiation shields in helical reactors, magnitudes of damage and radioactivation at the outboard divertors are almost two orders lower than those at blanket first walls. Cu materials could be used as a cooling channel material of the outboard divertors. In contrast, the magnitudes at the inboard divertors are only one order lower compared with those at the first walls due to the limited space at the inboard side. Damage on Cu is evaluated to be ～10 dpa after 6 years operation. Further efforts in divertor development and reactor design could suppress the magnitude of damage to less than half for adoption of Cu materials for the inboard divertors. |
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| Keywords: | Helical reactor Neutronics Divertor Irradiation damage Cu materials Radioactivation |
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