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Suzuki, Hideaki; Nakama, Shigeo; Fujita, Tomoo; Imai, Hisashi; Sazarashi, Masami
Genshiryoku Bakkuendo Kenkyu (CD-ROM), 19(2), p.39 - 50, 2012/12
For the safety assessment of a geological disposal system for high-level radioactive waste, it is necessary to quantify coupled thermo-hydro-mechanical-chemical (THMC) processes in the near-field. The current study investigated the geochemical changes arising from the infiltration of groundwater into the bentonite buffer under a thermal regime of radiogenic heating arising from the vitrified waste with the computer simulated assistance of a developed THMC model. In the case of infiltration by a saline groundwater, sulfate precipitates as gypsum around the overpack in the bentonite buffer and the Na-type bentonite changes to Ca-type by exposure to Ca ions released from concrete supports. In addition, the temporal evolution of the bentonite buffer porewater composition can be obtained to assess its contribution to the corrosion of the overpack.
Kimura, Makoto*; Sazarashi, Masami; Fujita, Tomoo; Nakama, Shigeo; Suzuki, Hideaki
JAEA-Research 2010-034, 131 Pages, 2010/10
JAEA-Research-2010-034.pdf:16.23MB
Numerical model which can quantify the complex evolution of the coupled thermo-hydro-mechanical-chemical processes in the near-field of a HLW repository has been developed and the outline of the model considering heat flow, fluid flow, mass transport and a variety of chemical reactions such as mineral dissolution/precipitation, gas dissolution/exsolution, ion-exchange and surface complexation are described. The applicability of the numerical model was shown by the following three efforts. (1) Intercomparison analysis against another coupled model, TOUGHREACT which has been developed in the Lawrence Berkeley National Laboratory. (2) Comparison with the measured data in the designed laboratory tests for the salt accumulation/precipitation. (3) Perspective simulation on chemical changes in the near-field involving the radioactive decay heat arising from the vitrified waste and infiltration of ground water into the buffer material.
Sasamoto, Hiroshi; Ishii, Tomoko*; Sato, Hisao*; Sazarashi, Masami
JAEA-Research 2010-030, 64 Pages, 2010/09
JAEA-Research-2010-030.pdf:15.41MB
It is necessary to evaluate the alteration behavior of buffer material by interactions of overpack (iron) and buffer (bentonite) materials for geological disposal of high level radioactive waste. In the present study, laboratory experiments were carried out for the better understanding of phenomena caused by iron-bentonite (smectite) interactions. Before conducting the experiments, literature survey was performed to summarize the existing knowledge about iron-bentonite interactions and to identify the dominant factors affecting the alteration behavior. As the results of experiment, experimental conditions caused remarkable alteration, secondary minerals suggested as alteration product, different behavior of alteration between batch and compacted systems etc. were revealed.
Fujita, Tomoo; Yui, Mikazu; Suzuki, Hideaki*; Fujisaki, Kiyoshi; Sazarashi, Masami*
JAEA-Research 2007-017, 47 Pages, 2007/03
JAEA-Research-2007-017.pdf:9.27MB
This report describes the results of a joint research entitled "Study on Simulation of Salt Accumulation" which was conducted under the collaboration between the Institute of Research and Innovation and the Japan Atomic Energy Agency. In the experiments for salt accumulation, accumulation of 
and 
was observed near the heater surface. Based on the facts from experiments, we have made hypothesis for mechanism of salt accumulation, and developed the model for it. Then, we conducted numerical simulations for salt accumulation phenomena under the saturated condition using the geochemical code "PHREEQC". It became clear that salt accumulation behavior can be evaluated qualitatively from these simulations, but quantitative evaluation requires more realistic modeling. Moreover we evaluated salt accumulation phenomena by simulations using coupled thermo - hydro - mechanical and chemical model / code assuming the unsaturated and / or saturated condition. A series of simulations were conducted focusing on accumulation of gypsum, and the result showed that tendency of salt accumulation phenomena was in agreement with that of experiments, but the profile of distribution of accumulated gypsum was not in agreement. In conclusion, it became clear that more realistic boundary condition should be considered and problems on coupled model / code were identified for further study.
Sazarashi, Masami*; ; Ikeda, Yasuhisa*; Kumagai, Mikio*; ;
PNC TJ1564 97-002, 20 Pages, 1997/03
None
Sazarashi, Masami*; Ikeda, Yasuhisa*; Kumagai, Mikio*; ;
PNC TJ1564 96-002, 19 Pages, 1996/03
None
Sazarashi, Masami*; Ikeda, Yasuhisa*; Kumagai, Mikio*
PNC TJ1564 93-003, 17 Pages, 1993/02
The present study has been carrisd out to establish the final disposal methods for e wastes containing radioactive iodines. In the previous studies, cinnabar (spain) a montmorillonite containing Ag-thiourea complex were selected as the arificial barri materials. In the present report, the adsorption mechanisms of two adsorbents were udied in more detail. Furthermore, various synthetic inorganic ion exchangers were ao examined as the model materials of I
ion adsorbents. The results are summarized afollow : 1. Detail examination for I ion adsorption behavior of cinnabar (1) In avaible cinnabars, only spain one has an adsorptivity to I ion. (2) The cinnabar adsorde has the selective adsorptivity to I ion. (3) It takes 40 days to reach the adsorpti equilibrium. (4) The amount of adsorbed I ions decreases with the rise of pH, and t desorption of I ions from cinnadar is not observed. These results suggest that thedsorption of I ions on cinnabar is not due to the ion exchange but the compo
Sazarashi, Masami*; Ikeda, Yasuhisa*; Kumagai, Mikio*
PNC TJ1564 93-002, 23 Pages, 1993/02
None
Sazarashi, Masami*; Ikeda, Yasuhisa*; Kumagai, Mikio*
PNC TJ1262 91-001, 168 Pages, 1991/05
None
Imai, Hisashi; Sazarashi, Masami; Suzuki, Hideaki; Fujita, Tomoo
no journal, ,
no abstracts in English
Suzuki, Hideaki; Nakama, Shigeo; Fujita, Tomoo; Imai, Hisashi; Sazarashi, Masami
no journal, ,
no abstracts in English
Sazarashi, Masami; Imai, Hisashi; Suzuki, Hideaki; Fujita, Tomoo
no journal, ,
no abstracts in English
Kimura, Makoto; Fujita, Tomoo; Sazarashi, Masami; Suzuki, Hideaki
no journal, ,
no abstracts in English
Sazarashi, Masami; Kimura, Makoto*; Suzuki, Hideaki; Fujita, Tomoo; Chijimatsu, Masakazu*
no journal, ,
no abstracts in English
Sasamoto, Hiroshi; Wilson, J.*; Sato, Hisao*; Sazarashi, Masami
no journal, ,
The proposed repository design for high-level radioactive waste in Japan includes iron containers surrounded by a bentonite buffer. Interactions of iron-bentonite (I/B) materials may lead to the adverse transformation of smectite to phases with a limited capacity to swell. Batch experiments that included native iron powder and bentonite and column experiments whereby compacted bentonites were reacted with embedded iron coupons were conducted in order to evaluate the effects of environmental parameters on I/B interactions. Additionally, several model simulations have been produced in order to evaluate the factors influencing the nature of bentonite alteration in the presence of iron. The dominant process of interest over performance assessment timescales was estimated as the results of variant simulations.
Taniguchi, Naoki; Suzuki, Hiroyuki; Kawasaki, Manabu; Watanabe, Masatoshi; Tateishi, Tsuyoshi*; Sazarashi, Masami
no journal, ,
Immersion tests of carbon steel were carried out in bentonite saturated with synthetic seawater between 30-160 
C. The corrosion depth was measured by weight loss of the specimens. The results showed that the initial corrosion rates increased with increasing temperature, and that the most protective corrosion product film was formed at 80-120 C. In order to evaluate the possibility of hydrogen embrittlement, the content of absorbed hydrogen (diffusive hydrogen) in specimens were analyzed. The results showed a tendency of decreasing the content of absorbed hydrogen with increasing temperature.
Nagatani, Mutsumi; Fujisaki, Kiyoshi*; Sazarashi, Masami; Fujita, Tomoo; Chijimatsu, Masakazu*
no journal, ,
no abstracts in English
Sazarashi, Masami; Imai, Hisashi; Suzuki, Hideaki; Fujita, Tomoo
no journal, ,
no abstracts in English
Sazarashi, Masami; Nagatani, Mutsumi; Kimura, Makoto; Suzuki, Hideaki; Fujita, Tomoo; Chijimatsu, Masakazu*
no journal, ,
no abstracts in English
Sazarashi, Masami; Taniguchi, Naoki; Naito, Morimasa; Tateishi, Tsuyoshi*
no journal, ,
no abstracts in English
