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Sekioka, Yasushi*; Takeda, Seiji; Kimura, Hideo
JAEA-Research 2009-062, 68 Pages, 2010/03
In safety assessment for geological disposal, release of radionuclides from vitrified waste is dependent on dissolution rate of glass matrix. It is assumed that the alteration and dissolution of glass in an engineered barrier system proceeds by a mechanism not related by the chemical affinity for dissolution reaction of glass matrix. Recent studies indicate that the glass dissolution rate is likely to decrease as time passed, but scientific basis on the dissolution process has not been necessarily understood. We estimate uncertainty of the glass dissolution rate represented by not only a model of constant dissolution rate but also a model of decreasing dissolution rate. In order to estimate the parameter uncertainty of the glass dissolution rate, we carried out the statistical analysis of the appropriate release rate data of boron for a hypothetical condition of disposal system, based on investigating the relation between published data of glass dissolution and those experimental conditions. As a result of the model of constant dissolution rate, the uncertainty of the glass dissolution rate is estimated to be a variance with about 3 orders and logarithmic mean of 0.004 g/m/day. The glass dissolution rate by the decreasing model changes in the range of 10 to 10 g/m/day by 1000 years and is lower than the minimum value estimated by the model of constant dissolution rate. The result indicates that the difference of two models may lead to large variance of the glass dissolution rate in safety assessment.
Takeda, Seiji; Yamaguchi, Tetsuji; Nagasawa, Hirokazu; Watanabe, Masatoshi; Sekioka, Yasushi; Kanzaki, Yutaka; Sasaki, Toshihisa; Ochiai, Toru; Munakata, Masahiro; Tanaka, Tadao; et al.
JAEA-Research 2009-034, 239 Pages, 2009/11
In safety assessment for geological disposal of high level radioactive waste, it is of consequence to estimate the uncertainties due to the long-term frame associated with long-lived radionuclides and the expanded geological environment. The uncertainties result from heterogeneity intrinsic to engineered and natural barrier materials, insufficient understanding of phenomena occurring in the disposal system, erroneous method of measurement, and incomplete construction. It is possible to quantify or to reduce the uncertainties according to scientific and technological progress. We applied a deterministic and a Monte Carlo-based probabilistic method simulation techniques to the uncertainty analysis for performance of hypothetical geological disposal system for high level radioactive waste. This study provides the method to evaluate the effects of the uncertainties with respect to scenarios, models and parameters in engineering barrier system on radiological consequence. The results also help us to specify prioritized models and parameters to be further studied for long-term safety assessment.
Sekioka, Yasushi; Takeda, Seiji; Kimura, Hideo; Yamaguchi, Tetsuji; Oe, Toshiaki*; Nagasaki, Shinya*; Sasaki, Takayuki*; Kozaki, Tamotsu*; Inagaki, Yaohiro*
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no abstracts in English
Oe, Toshiaki*; Nagasaki, Shinya*; Kimura, Hideo; Takeda, Seiji; Sekioka, Yasushi; Kato, Hiroyasu*; Akahori, Kuniaki*
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Takeda, Seiji; Sekioka, Yasushi; Yotsuji, Kenji; Kimura, Hideo; Inagaki, Yaohiro*
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Takeda, Seiji; Sasaki, Toshihisa; Sekioka, Yasushi; Kimura, Hideo
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Watanabe, Masatoshi; Takeda, Seiji; Sekioka, Yasushi; Kimura, Hideo
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Kimura, Hideo; Takeda, Seiji; Sasaki, Toshihisa; Sekioka, Yasushi
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Sasaki, Toshihisa; Takeda, Seiji; Sekioka, Yasushi; Kimura, Hideo
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Oe, Toshiaki*; Nagasaki, Shinya*; Kimura, Hideo; Takeda, Seiji; Sekioka, Yasushi; Kato, Hiroyasu*
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Kitamura, Akira; Sekioka, Yasushi*
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Solubility of palladium and tin has been experimentally investigated in the presence of -isosaccharinic acid (ISA). The obtained solubility increased with increasing concentration of ISA, especially for palladium.
Takeda, Seiji; Sekioka, Yasushi; Kimura, Hideo; Sasaki, Toshihisa
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no abstracts in English
Sawaguchi, Takuma; Takeda, Seiji; Kozaki, Tamotsu*; Sekioka, Yasushi; Kato, Hiroyasu*; Kimura, Hideo
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no abstracts in English