@article{oai:repo.qst.go.jp:00084327,
 author = {Matsuura, Hideaki and Suganuma, Takuro and Koga, Yuki and Naoi, Motomasa and Katayama, Kazunari and Otsuka, Teppei and Goto, Minoru and Nakagawa, Shigeaki and Hamamoto, Shinpei and Ishitsuka, Etsuo and Kenji, Tobita and Satoshi, Konishi and Ryoji, Hiwatari and Yoji, Someya and Yoshiteru, Sakamoto and Matsuura, Hideaki and Katayama, Kazunari and Otsuka, Teppei and Goto, Minoru and Nakagawa, Shigeaki and Hamamoto, Shinpei and Ishitsuka, Etsuo and Kenji, Tobita and Satoshi, Konishi and Ryoji, Hiwatari and Yoji, Someya and Yoshiteru, Sakamoto},
 journal = {Fusion Engineering and Design},
 month = {Aug},
 note = {The production of tritium (T) using high-temperature gas-cooled reactors (HTGRs) has been studied for a prior engineering research with T handling and initial T possession in demonstration fusion reactors. Stable containment of T in Li-loading rods during HTGR operation is a critical issue. This study investigates this for an irradiation test to examine T-containment performance in Li-loading rods and develops an analytical model of evaluating the amount of T outflow to a He coolant. The hydrogen absorption characteristics, including the deterioration of the hydrogen absorption speed after Zr has sufficiently absorbed the hydrogen, is experimentally measured assuming an HTGR setting. We present an analytical model of evaluating the T outflow from a Li rod and, on the basis of this model, estimate the total T outflow, assuming the presence of a gas-turbine high-temperature reactor of 300 MWe with a nominal capacity and a high-temperature engineering test reactor. It is demonstrated that, by loading a sufficient amount of Zr into the Li rod, the T outflow can be suppressed to less than a small percent of the total T produced during 360 days of reactor operation.},
 title = {The T-containment properties of a Zr-containing Li rod in a high-temperature gas-cooled reactor as a T production device for fusion reactors},
 volume = {169},
 year = {2021}
}