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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
JAEA-Research-2009-034.pdf:33.52MB
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.
Ochiai, Toru; Takeda, Seiji; Kimura, Hideo
JAEA-Data/Code 2009-003, 62 Pages, 2009/06
JAEA-Data-Code-2009-003.pdf:5.46MB
The objective of this study is to estimate the uncertainties on the soil-to-plant transfer factor in the safety assessment. The transfer factors for radionuclides used in the safety assessment were determined based on the results of statistical analysis for transfer factor data collected form literature survey and of comparison with the data published by IAEA. This report provides the determined values of the transfer factor, the process and grounds of determining them, and collected data of transfer factor as database.
Sawaguchi, Takuma; Takeda, Seiji; Sasaki, Toshihisa; Ochiai, Toru; Watanabe, Masatoshi; Kimura, Hideo
JAEA-Research 2008-046, 62 Pages, 2008/03
JAEA-Research-2008-046.pdf:3.34MB
The Atomic Energy Commission of Japan states that the transuranium waste and uranium waste are to be disposed of by either near surface disposal without artificial barrier (trench disposal), near surface disposal with artificial barrier (concrete vault disposal), or intermediate depth disposal, depending on the radionuclides and their radioactivity concentration in the wastes. The ranges of radioactivity concentration for these different disposal concepts are, therefore, required to be determined for the regulation. The radioactivity concentration limits define the upper bound of radioactivity concentrations for licensing application of the disposal of radioactive waste. This document summaries the concept and method for estimation of the radioactivity concentration limits for concrete vault disposal of transuranium and uranium wastes, and provides the derived values of the radioactivity concentration limits for each radionuclide in the wastes.
Takeda, Seiji; Sasaki, Toshihisa; Sawaguchi, Takuma; Ochiai, Toru; Kimura, Hideo
JAEA-Research 2008-045, 60 Pages, 2008/03
JAEA-Research-2008-045.pdf:3.51MB
This document summaries the concept and method (scenario selection, model/code description and parameter selection) for estimation of the radioactivity concentration limits for intermediate depth disposal of transuranium and uranium wastes, and provide the derived values of the radioactivity concentration limit for each radionuclide in the wastes. The values for the transuranium waste are published in a Nuclear Safety Commission of Japan report.
Takeda, Seiji; Watanabe, Masatoshi; Sawaguchi, Takuma; Sasaki, Toshihisa; Ochiai, Toru; Kimura, Hideo
JAEA-Research 2008-044, 64 Pages, 2008/03
JAEA-Research-2008-044.pdf:5.21MB
This document summaries the concept and method (scenario selection, model/code description and parameter selection) for estimation of the radioactivity concentration limits for trench disposal of transuranium and uranium wastes, and provide the derived values of the radioactivity concentration limit for each radionuclide in the wastes. The values for the transuranium waste are published in a Nuclear Safety Commission of Japan report.
Sasaki, Toshihisa; Watanabe, Masatoshi; Takeda, Seiji; Sawaguchi, Takuma; Ochiai, Toru; Kimura, Hideo
JAEA-Data/Code 2008-003, 29 Pages, 2008/02
JAEA-Data-Code-2008-003.pdf:3.7MBJAEA-Data-Code-2008-003(errata).pdf:0.04MB
In this report, external effective dose conversion factors necessary for examining the activity concentration limits are derived for three disposal concepts. After this, the activity concentration limits that constitute a permissible range of radioactive concentration to typical land disposal concept (for radioactive wastes containing transuranic nuclides from reprocessing and MOX fuel manufacturing and uranium waste from enrichment and fuel manufacturing) are calculated. External effective dose conversion factors are derived in consideration with analysis that conforms to laws that use the conversion coefficients of ICRP Publication 74 for effective dose conversion, and adoption of the latest data i.e. 
-ray's and X-ray's energies and intensities of "JAERI-Data/Code 2001-004" as photon energy data. This document summarizes calculation method, conditions, and results of external effective dose conversion factors for transuranium and uranium wastes disposal.
Kimura, Hideo; Takeda, Seiji; Sasaki, Toshihisa; Ochiai, Toru
no journal, ,
no abstracts in English
Sawaguchi, Takuma; Takeda, Seiji; Sasaki, Toshihisa; Ochiai, Toru; Watanabe, Masatoshi; Kimura, Hideo
no journal, ,
no abstracts in English