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Development of performance assessment models for glass dissolution

Published online by Cambridge University Press:  20 February 2017

T. Goto ,
S. Mitsui ,
H. Takase ,
S. Kurosawa ,
M. Inagaki ,
M. Shibata  and
K. Ishiguro
T. Goto*
Affiliation:
- Nuclear Waste Management Organization of Japan (NUMO)
S. Mitsui
Affiliation:
- Japan Atomic Energy Agency (JAEA)
H. Takase
Affiliation:
-Quintessa Japan
S. Kurosawa
Affiliation:
- Nuclear Waste Management Organization of Japan (NUMO)
M. Inagaki
Affiliation:
- Nuclear Waste Management Organization of Japan (NUMO)
M. Shibata
Affiliation:
- Japan Atomic Energy Agency (JAEA)
K. Ishiguro
Affiliation:
- Nuclear Waste Management Organization of Japan (NUMO)
*
*(Email: [email protected])
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Abstract

NUMO and JAEA have been conducting a joint research since FY2011, which is aimed to enhance the methodology of repository design and performance assessment in preliminary investigation stage for the deep geological disposal of high-level radioactive waste. As a part of this joint research, we have been developing glass dissolution models which include various processes derived from glass-overpack-bentonite buffer interaction, considering the precipitation of Fe-silicates associated with steel overpack corrosion, and Si transport through altered layer of glass. The objective of this modeling work is to show comprehensively the lifetime of the vitrified waste due to glass matrix dissolution timescales through sensitivity analysis, and to identify the feature/process that most strongly influences the lifetime, and to identify future R&D issues that would help to improve the nuclide transport analysis with confidential value and the safety case in future. The sensitivity analysis suggested that the duration of the glass dissolution might be predicted in the ranges from 3.8×103 to 1.9×105 years. Also, the results indicated that the precipitation of Fe–silicate has the strongest influence on the long-team behavior of vitrified waste.

Keywords

waste magagementcorrosionsimulation
Type
Articles
Information
MRS Advances , Volume 1 , Issue 63-64: Scientific Basis for Nuclear Waste Management XXXIX , 2016 , pp. 4239 - 4245
Copyright
Copyright © Materials Research Society 2017 

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References

REFERENCES

Mitsui, S. et al. , Scientific Basis for Nuclear Waste Management (Mat. Res. Soc. Symp. Proceedings vol. 1193), pp.397–404 (2009).CrossRefGoogle Scholar
Philippini, V. et al. , Journal of Nuclear Materials 348, pp.60–69 (2006).Google Scholar
Mayant, C. et al. , Physics and Chemistry of the Earth Parts A/B/C, vol. 33, pp 991–999 (2008).Google Scholar
Gin, S., Scientific Basis for Nuclear Waste Management (Mat. Res. Soc. Symp. Proceedings vol. 663), pp.207–216 (2001).Google Scholar
Gin, S. et al. , Nature Communication, 6, 6360 (2015).Google Scholar
Gin, S. et al. , Geochimica et Cosmochimica Acta, 151, pp. 68–85(2015).Google Scholar
Maeda, T. et al. , International Journal of Corrosion, vol. 2011, Article ID 796457.4–128 (2011).Google Scholar
Jollivet, P. et al. , Journal of Nuclear Materials, 420, pp. 508–518 (2012).Google Scholar
Fleury, B. et al. , Journal of Nuclear Materials, 442, pp. 17–28 (2013).Google Scholar
de Combarieu, G, et al. , Applied Geochemistry, 26, pp. 65–79 (2011).CrossRefGoogle Scholar
Michelin, A. et al. , Corrosion Science, 76, pp. 403–414 (2013).Google Scholar
Burger, E. et al. , Applied Geochemistry, 31, p.p.159–170 (2013)Google Scholar
Curti, E., Godon, N. and Vernaz, E., Mater. Res. Soc. Symp. Proc. 294, 163–170 (1993).Google Scholar
Pescatore, C., Radiochim. Acta 66/67, 389-394 (1994).Google Scholar
Maillard, S. and Iracane, D., Mater. Res. Soc. Symp. Proc. 506, 231–238 (1998).Google Scholar
Aertsens, M. and Van Iseghem, P., Proceedings of the European Nuclear Society Meeting, 339-343 (1999).Google Scholar
Kuwahara, H. et al. , AESJ, Fall meeting, I44 (2007). (in Japanese)Google Scholar
Jollivet, P. et al. , Journal of Nuclear Materials, 281, pp. 231–243(2000).Google Scholar
Frugier, P., Journal of Nuclear Materials, 380, pp. 8–21(2008).Google Scholar
Inagaki, Y., et al. , Journal of Nuclear Science and Technology Volume 49, No. 4, pp. 438–449 (2012).Google Scholar
Vernaz, E. et al. , Journal of Nuclear Materials, 298, Issues 1–2, pp. 27–36 (2001).Google Scholar
Schlegel et al., Applied Geochemistry, 23, p.p. 2619–2633(2008).Google Scholar
Taniguchi, N., et al. , JAEA-Research 2008-11, (2008). (In Japanese)Google Scholar
Sené, M. R. et al. , EUR 19119 EN. Luxembourg, Luxembourg: Commission of the European Communities. TIC: 254444 (1999).Google Scholar
JNC, JNC-TN1400 99-020 (1999).Google Scholar
Rebrenau, L. et al. , Marine Chemistry, 112, p.p. 230–233 (2008).Google Scholar
Philippini, V. et al. , Journal of Nuclear materials, 348, p.p. 60–69(2006).Google Scholar