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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: tgoto@numo.or.jp)
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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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