TY - JOUR
T1 - 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
AU - Matsuura, Hideaki
AU - Suganuma, Takuro
AU - Koga, Yuki
AU - Naoi, Motomasa
AU - Katayama, Kazunari
AU - Otsuka, Teppei
AU - Goto, Minoru
AU - Nakagawa, Shigeaki
AU - Hamamoto, Shinpei
AU - Ishitsuka, Etsuo
AU - Tobita, Kenji
AU - Konishi, Satoshi
AU - Hiwatari, Ryoji
AU - Someya, Youji
AU - Sakamoto, Yoshiteru
N1 - Funding Information:
This work was supported by JSPS (Japan Society for the Promotion of Science) KAKENHI Grant-in-Aid for Scientific Research (B) JP18H1200 and cooperative program with BA (The Joint Implementation of the Broader Approach Activities in the Field of Fusion Energy Research) reactor design team in Japan.
Publisher Copyright:
© 2021 Elsevier B.V.
PY - 2021/8
Y1 - 2021/8
N2 - 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.
AB - 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.
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U2 - 10.1016/j.fusengdes.2021.112441
DO - 10.1016/j.fusengdes.2021.112441
M3 - Article
AN - SCOPUS:85102818948
SN - 0920-3796
VL - 169
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
M1 - 112441
ER -