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Development of performance assessment models for glassdissolution

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: tgoto@numo.or.jp)
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Abstract

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

Keywords

waste magagementcorrosionsimulation

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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

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