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Sensitivity Analysis on Safety Functions of Engineered and Natural Barriers for Fuel Debris Disposal

Published online by Cambridge University Press:  16 January 2017

Taro Shimada*
Affiliation:
Nuclear Safety Research Center, Japan Atomic Energy Agency, 2-4 Shirakata, Tokai-mura, Ibaraki, 3191195, JAPAN.
Yuki Nishimura
Affiliation:
Nuclear Safety Research Center, Japan Atomic Energy Agency, 2-4 Shirakata, Tokai-mura, Ibaraki, 3191195, JAPAN.
Seiji Takeda
Affiliation:
Nuclear Safety Research Center, Japan Atomic Energy Agency, 2-4 Shirakata, Tokai-mura, Ibaraki, 3191195, JAPAN.
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Abstract

A disposal measure for fuel debris generated at the accident in the Fukushima Daiichi Nuclear Power Station has been studied so far. However, physical and chemical properties of the fuel debris located in reactor containment vessels have not yet been obtained. In order to investigate the safety function of barriers required for disposal of fuel debris, sensitivity analysis for radionuclide migration was carried out, considering with uncertainty of the properties. As a result, it is indicated that it was important for evaluation of fuel debris disposal to obtain the physical and chemical properties of 14C and 129I during release to groundwater, in addition to 238U.

Type
Articles
Copyright
Copyright © Materials Research Society 2017 

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References

REFERENCES

Kirishima, A. et. al., Leaching of actinide elements from simulated fuel debris into seawater. J Nucl Sci Technol, 52(10), 12401246, (2015).CrossRefGoogle Scholar
Sasaki, T. et. al., Leaching behavior of gamma-emitting fission products and Np from neutron-irradiated UO2–ZrO2 solid solutions in non-filtered surface seawater, J Nucl Sci Technol, 53(3), 303311, (2016).CrossRefGoogle Scholar
Takeda, S. et. al., Assessment on Long-term Safety for Geological Disposal of High Level Radioactive Waste, JAEA-Research 2009-034, (2009). [in Japanese]Google Scholar
JAEA, Preliminary Assessment of Geological Disposal System for Spent Fuel in Japan - First Progress Report on Direct Disposal - JAEA- Research 2015-016, (2015). [in Japanese]Google Scholar
Nishihara, K. et. al., Estimation of Fuel Compositions in Fukushima-Daiichi Nuclear Power Plant. JAEA-Data/Code 2012-018, (2012). [in Japanese]Google Scholar
JNC., 2nd Progress Report on Research and Development for the Geological Disposal of HLW in Japan, JNC Technical Report TN1410 2000-001, Japan Nuclear Cycle Development Institute, Tokai-mura Japan, (2000). [in Japanese]Google Scholar
Nagra (2002): Project Opalinus Clay Safety Report, NTB 02–05Google Scholar