关键词: 氚滞留量, 氚坑深度, 氚坑时间, 海绵效应, 氘和铍的伴同沉积, SPB方法

Abstract:

How high are the tritium retention on the first wall surface and the total tritium inventory in PFC materials of a fusion reactor？How much are the tritium well depth and tritium well time during a fusion reactor start-up and initial operation phase？How high tritium recovery efficiency can be obtained in the ITER TBM solid breeder blanket with using purge gas? Can we find some effective mechanisms to solve the above mentioned problems? All of these problems are decisive key issues on the way to achieve the ITER final anticipant goals and to attain realistic fusion energy application ultimately. In the first part of this article, the first two questions have been answered. Some innovative researches on above mentioned rest problems are performed and some new schemes for reducing tritium retention and improving tritium recovery efficiency are proposed in the second part of this article to be published next issue, such as, sponge mechanism based on deuterium saturated PFC materials; deuterium and beryllium co-deposition layer created on first wall surface; SPB scheme for enhancing isotope exchange rate and tritium recovery efficiency of purge gas in ceramic breeder blanket based on the catalyzed electrical polarization rotations, resulted from applied low frequency electric-field, of Li4SiO4 grain and purge gas molecular particles and so on，will be explored.

Key words: Tritium retention, Tritium well depth, Tritium well time, Sponge mechanism, Deuterium and beryllium co-deposition, SPB scheme