Measurement of HLW glass dissolution/alteration kinetics by using micro-reactor flow-through test method

Y. Inagaki, S. Mitsui, H. Makigaki, K. Idemitsu, T. Arima, T. Banba, K. Noshita

Research output: Chapter in Book/Report/Conference proceedingConference contribution

3 Citations (Scopus)


A new type of flow-through test method using micro-reactor was developed and applied to measurement of the dissolution/alteration kinetics for a Japanese type of simulated HLW glass, P0798. In this test method, a face of coupon shaped glass specimen (30mm x 10mm x 4mm size) is in contact with a micro-channel (20mm length, 2mm width, 0.16mm depth) constructed on a PTFE (Teflon®) plate, and a solution is injected into the inlet of micro-channel at a constant rate. The injected solution, which flows through the micro-channel reacting with the glass to the outlet, is retrieved at certain intervals to be analyzed for determination of the glass dissolution/alteration rate. After the test, the glass specimen removed from the micro-reactor is subjected to surface analyses. This test method has major features as follows, 1) any controlled solution condition can be provided over the test duration, 2) a relatively high S/V ratio can be provided by use of micro-reactor in spite of using coupon shaped glass specimen, which results in precise and consistent analyses of both the solution and the reacted glass surface, 3) the test apparatus is simple with compact size and easy operation, which allows a flexible setup of test conditions. By use of this test method the dissolution/alteration rate for P0798 glass was measured as a function of pH, temperature, and time, and the results indicated that this test method is applicable and suitable for evaluation of the dissolution/alteration kinetics.

Original languageEnglish
Title of host publicationScientific Basis for Nuclear Waste Management XXXIII
PublisherMaterials Research Society
Number of pages10
ISBN (Print)9781605111667
Publication statusPublished - 2009
Event32nd Symposium on Scientific Basis for Nuclear Waste Management - St. Petersburg, Russian Federation
Duration: May 24 2009May 29 2009

Publication series

NameMaterials Research Society Symposium Proceedings
ISSN (Print)0272-9172


Other32nd Symposium on Scientific Basis for Nuclear Waste Management
Country/TerritoryRussian Federation
CitySt. Petersburg

All Science Journal Classification (ASJC) codes

  • Materials Science(all)
  • Condensed Matter Physics
  • Mechanics of Materials
  • Mechanical Engineering


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