TY - JOUR
T1 - Evaluation of tritium behavior in concrete
AU - Furuichi, Kazuya
AU - Takata, Hiroki
AU - Katayama, Kazunari
AU - Takeishi, Toshiharu
AU - Nishikawa, Masabumi
AU - Hayashi, Takumi
AU - Kobayashi, Kazuhiro
AU - Namba, Haruyuki
N1 - Copyright:
Copyright 2009 Elsevier B.V., All rights reserved.
PY - 2007/8/1
Y1 - 2007/8/1
N2 - Concrete walls used in a fusion reactor or a tritium handling facility have the important role of separating the atmosphere in a facility from environmental air, since substantial tritium leakage is possible from a tritium system to the atmosphere of a tritium handling facility. Therefore, it is necessary to understand the transfer behavior of tritium through concrete. The experiments of this study were performed to observe the change of the tritium distribution with time in columns made of cement paste, mortar or concrete. It was found that exposure of the surface of concrete materials to HTO vapor for two months produced tritium permeation to the depth of 30 mm. Estimation of tritium penetration behavior was also performed in this study by applying adsorption, desorption and isotope exchange reactions and the estimated tritium profile was in good agreement with observed values.
AB - Concrete walls used in a fusion reactor or a tritium handling facility have the important role of separating the atmosphere in a facility from environmental air, since substantial tritium leakage is possible from a tritium system to the atmosphere of a tritium handling facility. Therefore, it is necessary to understand the transfer behavior of tritium through concrete. The experiments of this study were performed to observe the change of the tritium distribution with time in columns made of cement paste, mortar or concrete. It was found that exposure of the surface of concrete materials to HTO vapor for two months produced tritium permeation to the depth of 30 mm. Estimation of tritium penetration behavior was also performed in this study by applying adsorption, desorption and isotope exchange reactions and the estimated tritium profile was in good agreement with observed values.
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U2 - 10.1016/j.jnucmat.2007.03.227
DO - 10.1016/j.jnucmat.2007.03.227
M3 - Article
AN - SCOPUS:34447520238
SN - 0022-3115
VL - 367-370 B
SP - 1243
EP - 1247
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - SPEC. ISS.
ER -