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Derivation of an approximate analytical solution for understanding the response characteristics of the EBS

Published online by Cambridge University Press:  27 March 2012

T. Ohi ,
T. Chiba ,
T. Nakagawa ,
T. Takase ,
T. Nakazawa ,
Y. Akagi  and
K. Idemitsu
T. Ohi
Affiliation:
Nuclear Waste Management Organization of Japan (NUMO), 1-23, Shiba 4-chome, Minato-ku, Tokyo, 108-0014 Japan
T. Chiba
Affiliation:
JGC Corporation, 2-3-1 Minatomirai, Nishi-ku, Yokohama-shi, Kanagawa, 220-6001 Japan
T. Nakagawa
Affiliation:
JGC Corporation, 2-3-1 Minatomirai, Nishi-ku, Yokohama-shi, Kanagawa, 220-6001 Japan
T. Takase
Affiliation:
Mitsubishi Materials Corporation, 1-297 Kitabukuro-cho, Omiya-ku, Saitama-shi, Saitama, 330-8508 Japan
T. Nakazawa
Affiliation:
Mitsubishi Materials Corporation, 1-297 Kitabukuro-cho, Omiya-ku, Saitama-shi, Saitama, 330-8508 Japan
Y. Akagi
Affiliation:
Mitsubishi Materials Corporation, 1-297 Kitabukuro-cho, Omiya-ku, Saitama-shi, Saitama, 330-8508 Japan
K. Idemitsu
Affiliation:
Kyushu University, 744 Motooka, Nishi-ku, Fukuoka-shi, Fukuoka, 819-0395 Japan
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Abstract

To perform a safety assessment for the geological disposal of radioactive waste, it is important to understand the response characteristics of the disposal system. In this study, approximate analytical solutions for steady-state nuclide releases from the engineered barrier system (EBS) of a repository were derived for an orthogonal one-dimensional diffusion model. In these approximate analytical solutions, inventory depletion, decay during migration and the influence of groundwater flow in the excavation damaged zone (EDZ) were considered. These solutions were simplified by the Taylor theorem in order to clearly represent the response characteristics of the EBS. The validity of these solutions was shown by comparison with numerical solutions. The response characteristics of the EBS are useful for identifying target values for important parameters that would have the effect of improving the robustness of system safety. The robustness of the geological disposal system and the reliability of the safety assessment can thus potentially be improved using the approximate analytical solutions.

Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1475: Symposium NW – Scientific Basis for Nuclear Waste Management XXXV , 2012 , imrc11-1475-nw35-p45
Copyright
Copyright © Materials Research Society 2012

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References

REFERENCES

1. IAEA, Safety Assessment Methodology for Near Surface Disposal Facilities, Results of a co-ordinated research project, Volume 1, Review and enhancement of safety assessment approaches and tools (2004).Google Scholar
2. Ohi, T., Takase, H., Inagaki, M., Oyamada, K., Sone, T., Mihara, M., Ebashi, T. and Nakajima, K., Mater. Res. Soc. Symp. Proc. Vol. 985, Scientific Basis for Nuclear Waste Management XXX, pp 129–134 (2006).10.1557/PROC-985-0985-NN03-21Google Scholar
3. Crank, J., The Mathematics of Diffusion, second edition, Oxford Science Publications (1975).Google Scholar
4. Chambre, P L., Pigford, T. H., Lee, W. W.-L., Ahn, J., Kajiwara, S., Kim, C. L., Kimura, H., Lung, H., Williams, W. J. and Zavoshy, S. J., Mass transfer and transport in a geologic environment, LBL-19430 (1985).10.2172/5161610Google Scholar
5. Zavoshy, S. J., Chambre, P. L., Ahn, J., Pigford, T. H. and Lee, W. W-L., Steady-state radionuclide transfer from a cylinder intersected by a fissure, LBL-23986 (1988).10.2172/6915130Google Scholar
6. Ahn, J., Chambre, P.L. and Pigford, T.H., Transient of diffusion from a waste solid into fractured porous Rock, LBL-24576 (1988).Google Scholar
7. Jnc, Jnc TN1410 2000-001 (2000).Google Scholar
8. Jnc, Jnc TN1410 2000-004 (2000).Google Scholar
9. FEPC & JNC, JAEA-Review 2007-010, FEPC TRU-TR2-2007-01 (2007).Google Scholar
10. SKB, Long-term safety for KBS-3 repositories at Forsmark and Laxemar – a first evaluation, Main Report of the SR-Can project (2006).Google Scholar
11. Ohi, T. and Nakajima, K., Mater. Res. Soc. Symp. Proc. Vol. 465, Scientific Basis for Nuclear Waste Management XX, pp 1091–1098 (1997).10.1557/PROC-465-1091Google Scholar
12. Mitsui, S., Makino, H., Inagaki, M. and Ebina, T., Mater. Res. Soc. Symp. Proc. Vol. 1193, Scientific Basis for Nuclear Waste Management XXXIII, pp 397–404(2009).10.1557/PROC-1193-397Google Scholar
13. Suzuki, S., Aoki, H., Kawakami, H., Hata, A. and Motoshima, T., Journal of Nuclear Fuel Cycle and Environment Vol. 15 No.2 pp 87–98 (2009) (in Japanese).10.3327/jnuce.15.87Google Scholar
14. NUMO, NUMO-TR-10-06 (2011) (in Japanese).Google Scholar