Diffusion of uranium in compacted bentonite in the presence of carbon steel

Kazuya Idemitsu, H. Furuya, Y. Tachi, Yaohiro Inagaki

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

10 Citations (Scopus)

Abstract

The objective of the present study is to investigate the diffusion of uranium in compacted bentonite under reducing and oxidizing conditions. The apparent diffusivities of uranium were measured in some bentonite specimens with carbon steel and in others without carbon steel. The diffusivities and the difference of the diffusivities between the two conditions are discussed.

Original languageEnglish
Title of host publicationScientific Basis for Nuclear Waste Management XVII
PublisherPubl by Materials Research Society
Pages939-946
Number of pages8
ISBN (Print)1558992324
Publication statusPublished - Jan 1 1994
EventProceedings of the 17th Materials Society Symposium - Boston, MA, USA
Duration: Nov 29 1993Dec 3 1993

Publication series

NameMaterials Research Society Symposium Proceedings
Volume333
ISSN (Print)0272-9172

Other

OtherProceedings of the 17th Materials Society Symposium
CityBoston, MA, USA
Period11/29/9312/3/93

All Science Journal Classification (ASJC) codes

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

Fingerprint Dive into the research topics of 'Diffusion of uranium in compacted bentonite in the presence of carbon steel'. Together they form a unique fingerprint.

  • Cite this

    Idemitsu, K., Furuya, H., Tachi, Y., & Inagaki, Y. (1994). Diffusion of uranium in compacted bentonite in the presence of carbon steel. In Scientific Basis for Nuclear Waste Management XVII (pp. 939-946). (Materials Research Society Symposium Proceedings; Vol. 333). Publ by Materials Research Society.