Radwaste management aspects of the test blanket systems in ITER

• Published in: Fusion engineering and design Vol. 109-111; pp. 222 - 226
• Main Authors: van der Laan, J.G., Canas, D., Chaudhari, V., Iseli, M., Kawamura, Y., Lee, D.W., Petit, P., Pitcher, C.S., Torcy, D., Ugolini, D., Zhang, H.
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01-11-2016
• Subjects: Characterization; Decommissioning; ITER; Nuclear; Test Blanket Systems; Waste; Characterization; ITER; Nuclear; Decommissioning; Waste; Test Blanket Systems
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2016.03.022

•Test Blanket Systems are operated in ITER to test tritium breeding technologies.•The in-vessel parts of TBS become radio-active during the ITER nuclear phase.•For each TBM campaign the TBM, its shield and the Pipe Forests are removed.•High tritium contents and novel materials are specific TBS radwaste features.•A preliminary assessment confirmed RW routing, provided its proper conditioning.
Test Blanket Systems (TBS) will be operated in ITER in order to prepare the next steps towards fusion power generation. After the initial operation in H/He plasmas, the introduction of D and T in ITER will mark the transition to nuclear operation. The significant fusion neutron production will give rise to nuclear heating and tritium breeding in the in-vessel part of the TBS. The management of the activated and tritiated structures of the TBS from operation in ITER is described. The TBS specific features like tritium breeding and power conversion at elevated temperatures, and the use of novel materials require a dedicated approach, which could be different to that needed for the other ITER equipment.