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Improvement of tritium accountancy technology for ITER fuel cycle safety enhancement

S. O'hira, T. Hayashi, H. Nakamura, K. Kobayashi, T. Tadokoro, H. Nakamura, T. Itoh, T. Yamanishi, Y. Kawamura, Y. Iwai, T. Arita, T. Maruyama, T. Kakuta, S. Konishi, M. Enoeda, M. Yamada, T. Suzuki, M. Nishi, T. Nagashima and M. Ohta

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In order to improve the safe handling and control of tritium for the ITER fuel cycle, effective in situ tritium accounting methods have been developed at the Tritium Process Laboratory in the Japan Atomic Energy Research Institute under one of the ITER-EDA R&D tasks. The remote and multilocation analysis of process gases by an application of laser Raman spectroscopy developed and tested could provide a measurement of hydrogen isotope gases with a detection limit of 0.3 kPa analytical periods of 120 s. An in situ tritium inventory measurement by application of a `self-assaying' storage bed with 25 g tritium capacity could provide a measurement with the required detection limit of less than 1% and a design proof of a bed with 100 g tritium capacity.


PACS

52.55.Fa Tokamaks, spherical tokamaks

52.70.-m Plasma diagnostic techniques and instrumentation

Subjects

Instrumentation and measurement

Plasma physics

Dates

Issue 3Y (March 2000)

Received 30 November 1998, accepted for publication 31 March 1999



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