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Kolbasov, B. N.*; El-Guebaly, L.*; Khripunov, V. I.*; Someya, Yoji; Tobita, Kenji; Zucchetti, M.*
Fusion Engineering and Design, 89(9-10), p.2013 - 2017, 2014/10
Times Cited Count：9 Percentile：57.19(Nuclear Science & Technology)Within the framework of the International Energy Agency Program on Environmental, Safety and Economic Aspects of Fusion Power, an international collaborative study on management of fusion radioactive materials has been carried out to examine the back-end of the materials cycle. The strategy for handling fusion activated materials calls for three potential schemes: clearance, recycling and disposal. There is a growing international effort to avoid geologic disposal, for fusion in particular. Plasma facing components (divertor and blanket) normally contain high radioactivity and are not clearable. As clearance of sizeable components (such as biological shield, cryostat vessel, vacuum vessel, and some constituents of magnets) is highly desirable, we identified the source of radioisotopes that hinder the clearance of these components and investigated the impact of impurity control. Another study assessed radioactivity build up under repeated use of the divertor made of W-La
O
alloy. Effect of impurities on activated materials management is illustrated by the example of carbon-14 generation. Other studies examined impurities activation in concrete of biological shield and the impact of a specific activated materials scenario on the hot cell design and waste storage requirements.
Iida, Hiromasa; Petrizzi, L.*; Khripunov, V.*; Federici, G.*; Polunovskiy, E.*
Fusion Engineering and Design, 75(1-4), p.133 - 139, 2005/11
The design of the ITER machine was presented in 2001. A nuclear analysis has been performed on ITER by means of the most detailed models and the best assessed nuclear data and codes. As the construction phase of ITER is approaching, the design of the main components has been optimized/finalized and several minor design changes/optimizations have been made, which required refined calculations to confirm that nuclear design requirements are met. Some of the proposed design changes have been made to mitigate critical radiation shielding problems. This paper reviews some of the most recent neutronic work with emphasis on critical nuclear responses in the TF coil inboard legs and vacuum vessel related to design modifications made to the blanket modules and vacuum vessel.
Uno, Yoshitomo; Kaneko, Junichi; Nishitani, Takeo; Maekawa, Fujio; Tanaka, Teruya; Shibata, S.*; Ikeda, Yujiro; Khripunov, V.*; Walker, C. I.*; Ebisawa, Katsuyuki*; et al.
Fusion Engineering and Design, 56-57, p.895 - 898, 2001/10
Times Cited Count：8 Percentile：52.36(Nuclear Science & Technology)no abstracts in English
