Crack formation in cementitious materials used for an engineering barrier system and their impact on hydraulic conductivity from the viewpoint of performance assessment of a TRU waste disposal system

Fumio Hirano, Yoshiteru Otani, Hiroyuki Kyokawa, Morihiro Mihara, Hiroyuki Shimizu, Akira Honda

Research output: Contribution to journalArticlepeer-review

1 Citation (Scopus)

Abstract

The mechanical analysis code MACBECE2014 has been developed at the Japan Atomic Energy Agency (JAEA) to make realistic simulations of the physical integrity of the near field for performance assessment of the geological disposal of TRU waste in Japan. The MACBECE2014 code can be used to evaluate long-term changes in the mechanical behavior of the near field and any subsequent changes in the permeability of engineering barrier components, including crack formation in cementitious materials caused by expansion due to metal corrosion. Cracks in cementitious materials are likely to channel the flow of groundwater and so the represent preferred flow paths of any released radionuclides. Mechanical analysis was conducted using the MACBECE2014 code to investigate the concept of the TRU waste disposal system described in JAEA's Second Progress TRU Report. Simulated results of a disposal system with a bentonite buffer demonstrated that the low permeability of the engineering barrier system could be maintained for long time periods because the physical integrity of the bentonite buffer remained intact even if cracks in the cementitious components had formed locally. Simulated results of the disposal system with a concrete backfill instead of a bentonite buffer showed that crack formation leads to a significant increase in the permeability of the engineering barrier system.

Original languageEnglish
Pages (from-to)97-114
Number of pages18
JournalTransactions of the Atomic Energy Society of Japan
Volume15
Issue number2
DOIs
Publication statusPublished - 2016 Jan 1

Keywords

  • Cementitious materials
  • Corrosion
  • Cracking
  • Engineering barrier
  • Geological disposal
  • Hydraulic conductivity
  • Mechanical behavior
  • Near field
  • Nuclide migration
  • Performance assessment
  • TRU waste

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality

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