H. Obayashi

H. Yamanishi

K. Watanabe

Y. Sakuma

National Institute for Fusion Science (NIFS-Repository)

§8. Tritium Inventory in the Large Helical De-vice Watanabe, K. (Toyama Univ.) Sakuma, Y., Yamanishi, H., Obayashi, H. A series of discussion meetings on the tritium issues in the LHD experimental program has been organized. 1. Scope of the meeting It is expected that the DD experiment with Large Helical Device, beginning at 2000, will produce tritium amounting to 12Ci/year ( 430GBq/year). A part of it will be removed with tritium recovering system, but another part will be captured by the first wall, the divertor, walls of pipe lines and so on. The o bj ecti ve of this discussion meeting is to find out the problems on evaluating distribution on analyse the tritium inventory the system and to present status of tritium-material interaction studies, accumulation of data base and R&Ds concerning to the tritium handling in the LHD. 2. Meeting in this fiscal year The first meeting was held on August 25 and the second was on December 17 in ·1993. At the first meeting, major topics were the LHD operation modes and established tritium production rate. Discussions were followed by the issues concerning to contamination and decontamination, tritium waste handling, monitoring and exposure control. The topics at the second meeting were experiences of DD and DT shots in the JT-60U and the TFTR, respectively, and environmental aspects at the Toki-site. 3. Meeting summaries 270 Tritium behavior in the LHD is belonging to the problems of low level tritium in a large complex volume. This does not mean, however, the ease of the tritium handling, because tritium release to the environment is expected to be severely limited at the Toki -site. The experiences of the JT-60U and the TFTR could be properly utilized to design the tritium handling system of the LHD. With this respect, evaluation of tritium inventory distribution is desirable with use of available data base at present and it is important to establish the principle of tritium hazard protection appropriate to the LHD device and the site environment, according to which suitable tritium handling systems could be applied It should be also recognized that the LHD device is a model machine to investigate tritium behavior in larger and more complex DT burning experimental machines such as the ITER. 

Tritium Inventory in the Large Helical Device

Abstract

Similar works

Full text

Available Versions

National Institute for Fusion Science (NIFS-Repository)