Journal of Radioanalytical and Nuclear Chemistry

, Volume 116, Issue 1, pp 13–25 | Cite as

Hydrogen production in α-irradiated bentonite

  • T. E. Eriksen
  • H. Christensen
  • E. Bjergbakke
Article

Abstract

The hydrogen production in α-irradiated (dose rate 0.73 Gy·s−1), compacted, water-saturated bentonite (ρ=2.12 g·cm−3) has been determined experimentally, using a gas-chromatographic technique. Hydrogen concentration in the clay pore water and hydrogen diffusion out of the irradiated bentonite have been calculated using a homogeneous reaction model. The calculated hydrogen transport out of the bentonite depends on the Fe2+ and HCO 3 concentration in the pore water. Agreement between experimental and calculated results can be obtained if it is assumed that a 20 μm layer of water is formed between, the clay and the α-source.

Keywords

Hydrogen Clay Bentonite Pore Water Dose Rate 

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References

  1. 1.
    V. I. SPITSYN, B. D. BALUKOVA, M. K. SAVUSHKINA, Influence of Irradiation with Gamma-quanta and Beam of Accelerated Electrons on the Sorption Parameters of Clay Minerals of the Montmorrillonite Group, in S. TOPP (Ed.) Scientific Basis for Nuclear Waste Management Vol 4, Elsevier, New York, 1982, p. 703.Google Scholar
  2. 2.
    D. B. CURTIS, A. J. GANCARZ, Radiolysis in nature: Evidence from the Oklo natural reactors, KBS-TR 83-10, 1983.Google Scholar
  3. 3.
    I. NERETNIEKS, The movement of a redox front downstream from a repository for nuclear waste, KBS-TR 82-16, 1982.Google Scholar
  4. 4.
    I. NERETNIEKS, B. ÅSLUND, Two-dimensional movements of a redox front downstream from repository for nuclear waste, KBS-TR 83-68, 1983.Google Scholar
  5. 5.
    T. E. ERIKSEN, A. JACOBSSON, Radiation effects on the chemical environment in a radioactive waste repository, KBS-TR 83-27, 1982.Google Scholar
  6. 6.
    H. CHRISTENSEN, E. BJERGBAKKE, Radiolysis of ground water from HWL stored in copper canisters, KBS-TR 82-02, 1982.Google Scholar
  7. 7.
    P. COHEN, Water coolant technology of power reactors, Gordon and Breach, New York, 1969.Google Scholar
  8. 8.
    N. BIBLER, J. Phys Chem, 78 (1974) 211.CrossRefGoogle Scholar
  9. 9.
    W. G. BURNS, H. E. SIMIC, J. Chem. Soc. Faraday Trans. I, 77 (1981) 2803.CrossRefGoogle Scholar
  10. 10.
    H. CHRISTENSEN, E. BJERGBAKKE, Radiolysis of ground water from spent fuel, KBS-TR 82-18, 1982, p. 16.Google Scholar
  11. 11.
    H. CHRISTENSEN, Nukleonik, 8 (1996) 121.Google Scholar
  12. 12.
    T. E. ERIKSEN, A. JACOBSSON, T. CARLSSON, Progress Report 1986-05-29.Google Scholar

Copyright information

© Akadémiai Kiadó 1987

Authors and Affiliations

  • T. E. Eriksen
    • 1
  • H. Christensen
    • 2
  • E. Bjergbakke
    • 3
  1. 1.Department of Nuclear ChemistryThe Royal Institute of TechnologyStockholm 70Sweden
  2. 2.Studsvik EnergiteknikNyköpingSweden
  3. 3.Risø National LaboratoryRoskildeDenmark

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