Tritium Release from PbLi Natural Convection Loop Under Neutron Irradiation
Fusion Science and Technology / Volume 62 / Number 1 / July/August 2012 / Pages 295-299
Fusion Technology Facilities / Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology / dx.doi.org/10.13182/FST12-A14150
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A PbLi thermal convection loop with the flow rate of a few centimeters per second was designed and constructed to perform an in-situ tritium release experiment in a neutron source of the YAYOI reactor of The University of Tokyo. Tritium was generated by the nuclear reaction of Li with neutrons released through a 1-mm-thick steel tube and followed the reactor power with some time lag, which was affected by the hydrogen concentration in the sweep gas. The overall permeation rate coefficients, around 10-5 m/s, were almost the same as those acquired in former works performed in static tests. Formation or reduction of a surface oxide layer on the permeation tube would affect the tritium release behavior.
