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Instant Release of 14C, 99Tc, 90Sr and 137Cs from Used Candu Fuel at 25°C in Distilled Deionized Water

Published online by Cambridge University Press:  25 February 2011

S. Stroes-Gascoyne
Affiliation:
AECL Research, Whiteshell Laboratories, Pinawa, Manitoba, Canada
J.C. Tait
Affiliation:
AECL Research, Whiteshell Laboratories, Pinawa, Manitoba, Canada
N.C. Garisto
Affiliation:
AECL Research, Whiteshell Laboratories, Pinawa, Manitoba, Canada
R.J. Porth
Affiliation:
AECL Research, Whiteshell Laboratories, Pinawa, Manitoba, Canada
J.P.M. Ross
Affiliation:
AECL Research, Whiteshell Laboratories, Pinawa, Manitoba, Canada
G.A. Glowa
Affiliation:
AECL Research, Whiteshell Laboratories, Pinawa, Manitoba, Canada
T.R. Barnsdale
Affiliation:
AECL Research, Whiteshell Laboratories, Pinawa, Manitoba, Canada
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Abstract

Instant-release fractions were measured for release of 14C, 99Tc, 90Sr and 137Cs from segments of clad used CANDU fuels in distilled deionized water at pH 8.5 and 25°C. Measured–instant release values, 0.002 to 0.07% for 14C, 0.001 to 0.23% for 99Tc and 0.0005 to 0.04% for 9 0 Sr, were one to two orders of magnitude lower than the estimated values currently used in the safety assessment of the Canadian concept of geological disposal of intact used CANDU fuel. The values for 14C were also lower than values reported in the literature for PWR fuels.

Type
Research Article
Copyright
Copyright © Materials Research Society 1992

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References

REFERENCES

1. Johnson, L.H., Crostwaithe, J.L., Gray, M.N., Ikeda, B.M. and Tait, J.C., Radio-active Waste Management and the Nuclear Fuel Cycle 8, 105 (1987).Google Scholar
2. Garisto, N.C., Johnson, L.H. and Hocking, W.H., in Proc. Second Int. Conf. on CANDU Fuel, Chalk River, 0, Oct. 1-5, 1989 ( Hastings, I.J., Ed.), 352 (1990).Google Scholar
3. Stroes-Gascoyne, S., Johnson, L.H. and Sellinger, D.M., Nucl. Technol. 77 320 (1987).Google Scholar
4. Stroes-Gascoyne, S. and Sellinger, D.M., in Proc. First Int. Conf. on CANDU fuel, Chalk River, 0, Oct. 6-8, 1986 ( Hastings, I.J., Ed.), 383 (1987).Google Scholar
5. Van, R.A. Konynenburg, Smith, C.F., Culham, H.W. and Smith, H.D., Mat. Res. Soc. Symp. Proc. 84, 185 (1987).Google Scholar
6. Wasywich, K.M., Atomic Energy of Canada Limited Report, AECL-XXXXX (1991, in prep.)Google Scholar
7. Wilson, C.N. and Shaw, H.F., Mat. Res. Soc. Symp. Proc. 84, 123 (1987).Google Scholar
8. Wilson, C.N., Pacific Northwest Laboratory Report, PNL-7169 (1990).Google Scholar
9. Wilson, C.N., Pacific Northwest Laboratory Report, PNL-7170 (1990).Google Scholar
10. Neal, W.L., Rawson, S.A. and Murphy, W.M., Mat. Res. Soc. Symp. Proc. 112, 505 (1988).Google Scholar
11. Tait, J.C., Gauld, I.C. and Wilkin, G.B., Atomic Energy of Canada Limited report, AECL-9881 (1989).Google Scholar
12. Konynenburg, R.A. Van, Smith, C.F., Culham, H.W. and Otto, C.H. Jr., Mat. Res. Soc. Symp. Proc. 44, 405 (1985).CrossRefGoogle Scholar
13. Kleykamp, H., J.Nucl. Mat. 84, 109 (1979).CrossRefGoogle Scholar
14. Prussin, S.G., Olander, D.R., Lau, W.K. and Hansson, L., J.Nucl. Mat. 154, 25 (1988).Google Scholar