Abstract
A comprehensive analysis of routine radiochemistry data obtained at a BWR plant has been performed. The variation of fission product release levels as well as the characteristics of the release pattern were evaluated. The number of defective fuel bundles and the exposures of the defective fuel are correctly predicted from the results of data analyses.
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W. J. Bailey, S. Wu, Fuel Performance Annual Report for 1987, NUREG/CR-3950, Vol. 5, 1989; Nucleonics Week 29 (45): 6–7 (Nov. 10, 1988).
J. M. Skarpelos, R. S. Gilbert, Technical Derivation of BWR 1971 Design Basis Radioactive Material Source Terms, General Electric Company, NEDO-10871, March 1971.
C. C. Lin, Radiochemistry in Nuclear Power Reactors, NAS-NS-3119, National Research Council, National Academy Press, Washington, D. C. 1996.
J. Santucci et al., Failed Fuel Action Plan Guideline, EPRI NP-5521-SR, Nov. 1987.
T. A. Green, Monitoring Fuel for Defects, Power, August 1978, p. 56.
M. O. Marlowe et al., Nuclear Fuel Cladding Localized Corrosion, ANS Intern. Topical Meeting on Light Water Reactor Fuel Performance, April 21–24, 1985, Orlando, Florida.
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Lin, C.C., Skarpelos, J.M. Monitoring of fission product release in a boiling water reactor. J Radioanal Nucl Chem 220, 173–181 (1997). https://doi.org/10.1007/BF02034852
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DOI: https://doi.org/10.1007/BF02034852