Gamma-ray dose analysis for ITER JA WCCB-TBM |
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| Affiliation: | 1. Japan Atomic Energy Agency, Tokai-mura, Ibaraki, Japan;2. Japan Atomic Energy Agency, Naka-shi, Ibaraki, Japan;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. CIEMAT, Madrid, Spain;2. IREC, Barcelona, Spain;3. GALVANO-T, Windeck, Germany;4. CARMAN, Madrid, Spain;5. TRINOS VACUUM, Valencia, Spain;1. Institute of Plasma Physics, AS CR v.v.i., Prague, Czech Republic;2. Institute of Energy and Climate Research – Plasma Physics, Forschungszentrum Juelich, Germany;3. Ecole Nationale Superieure des Arts et Metiers, France;4. CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France;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. ENEA Brasimone, Camugnano, Bologna, Italy;2. Dipartimento di Energia, Ingegneria dell’Informazione e Modelli Matematici, Università di Palermo, Viale delle Scienze, Palermo, Italy;3. ENEA Bologna, Via Martiri di Monte Sole 4, Bologna, Italy |
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| Abstract: | To evaluate the nuclear properties of the International Thermonuclear Experimental Reactor (ITER) JA Water-Cooled Ceramic Breeder Test Blanket Module (WCCB-TBM) and to ensure its design conforms to nuclear licensing regulations, nuclear analyses have been performed for the WCCB-TBM's components, including its frame, shield, flange, port extension, pipe forest, bio-shield and Ancillary Equipment Unit (AEU). Utilising Monte Carlo code MCNP5.14, activation code ACT-4 and the Fusion Evaluated Nuclear Data Library FENDL-2.1, this paper focusses on the shutdown dose rate calculation for the WCCB-TBM. Monte Carlo N-Particle Transport Code (MCNP) geometry input data for the TBM are created from computer-aided design (CAD) data using the CAD/MCNP automatic conversion code GEOMIT, and other geometry input data are created manually. The ‘Direct 1-Step Monte Carlo’ method is adopted for the decay gamma-ray dose rate calculation. Behind the bio-shield, the effective dose rates 1 day after shutdown are about 0.2 μSv h−1, which are much lower than 10 μSv h−1, the upper limit for human access. Behind the flange, the effective dose rates 106 s after shutdown are 50–80 μSv h−1, which are lower than 100 μSv h−1, the upper limit for human hands-on access for workers performing maintenance. |
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| Keywords: | ITER TBM MCNP GEOMIT D1S Shutdown dose rate |
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