Hostname: page-component-78c5997874-v9fdk Total loading time: 0 Render date: 2024-11-05T16:06:04.030Z Has data issue: false hasContentIssue false
  • English
  • Français

Alpha-Radiolysis of Aqueous Solutions

Published online by Cambridge University Press:  28 February 2011

Hilbert Christensen  and
Erling Bjergbakke
Hilbert Christensen
Affiliation:
Studsvik Energiteknik AB, S-611 82 Nyköping, Sweden
Erling Bjergbakke
Affiliation:
Risö National Laboratory, DK-4000 Roskilde, Denmark
Get access

Abstract

The effects of the radiolysis of water exposed to mixed alpha- and beta-radiation originating from spent fuel have been calculated. The water is assumed to have penetrated the copper canister and fuel cladding, and then to exist as a 30 μm thin surface film on the fuel pellets.

The combined effects of alpha and beta-radiation, and the presence of iron in the water have been found to be important parameters. The beta-radiation will lower the yield of hydrogen, as will the presence of low concentrations of iron ions. The most likely conditions for water exposed fuel give rise to a total production of 1 mol H2 per m2 fuel surface after 1 million years. A stoichiometric amount of oxygen is also formed.

Calculations have also been carried out in connection with experiments on alpha-radiolysis from Am-241 or from spent fuel pellets. In the case of alpha-radiolysis from Am-241 it was calculated that a 20 cm2 thin layer of 4 mCi Am-241 produced 1.4 × 10−3 cm3 hydrogen per day.

Calculations simulating the conditions of experiments on the leaching of spent fuel have shown that both alpha- and gamma-radiation accelerate the dissolution. The rate is strongly dependent on the dose rate and on the area of the water film covering the fuel surface and fuel fissures.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 50: Symposium STOCKHOLM – Scientific Basis for Nuclear Waste Management IX , 1985 , 401
Copyright
Copyright © Materials Research Society 1985

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

1. Neretnieks, I., The Movement of a Redox Front Downstreams From a Repository for Nuclear Waste, KBS TR 82−16, 1982.Google Scholar
2. Christensen, H. and Bjergbakke, E., Radiolysis of Ground Water From HLW Stored in Copper Canisters, KBS TR 82−02, 1982.Google Scholar
3. Rasmussen, O. L. and Bjergbakke, E., Chemisimul-a Program Package for Numerical Simulation of Chemical Reaction Systems, Risö-R-395, 1984.Google Scholar
4. Gear, C. W., Algorithm 407, DIFSUB, Commun. ACM, 14, 185 (1971).Google Scholar
5. Cohen, P., Water Coolant Technology of Power Reactors, (Gordon and Breach, New York, 1969) p 93.Google Scholar
6. Bibler, N., J. Phys. Chem., 78, 211 (1974).Google Scholar
7. Allen, A. O., The Radiation Chemistry of Water and Aqueous Solutions, (D. van Nostrand, Princeton, 1961).Google Scholar
8. Burns, W. G. and Sims, H. E., J. Chem. Soc., Farady Trans. 1, 77, 2803 (1981).Google Scholar
9. Lundgren, K., Radiation Levels and Absorbed Doses Around Copper Canisters Containing Spent LWR Fuel, KBS TR 82−11, 1982.Google Scholar
10. Lundgren, K., Strålningsnivå och till vatten deponerad strålnings-energi utanför kapslar i slutförvaret, (in Swedish), KBS TR-106, 1978.Google Scholar
11. Neretnieks, I. and Skagius, E., Diffusivitetsmätningar av metan och väte i våt lera, (in Swedish), KBS TR-86, 1978.Google Scholar
12. Eriksen, T., (private communication), 1984−01−11.Google Scholar
13. Forsyth, R. S. and Werme, L., The corrosion of spent UO2 fuel in synthetic groundwater, this volume.Google Scholar
14. Gromov, V., Radiat. Phys. Chem., 18, 135 (1981).Google Scholar
15. Allard, B., Torstenfelt, B. and Andersson, K. in Scientific Basis for Nuclear Waste Management III, edited by J., Moore (Elsevier Science Publishing Co., New York, 1981) p 465.Google Scholar