Fission Product Appearance Rate Coefficients in Design Basis Source Term Determinations – Past and Present
1 AREVA SAS, Lyon, France
2 AREVA INC, Marlborough, MA, U.S.A.
* Corresponding author: firstname.lastname@example.org
** Retired, currently ENTECH Engineering, Westborough, MA, U.S.A.
Published online: 25 September 2017
Nuclear power plant radiation protection design features are based on radionuclide source terms derived from conservative assumptions that envelope expected operating experience. Two parameters that significantly affect the radionuclide concentrations in the source term are failed fuel fraction and effective fission product appearance rate coefficients. Failed fuel fraction may be a regulatory based assumption such as in the U.S. Appearance rate coefficients are not specified in regulatory requirements, but have been referenced to experimental data that is over 50 years old. No doubt the source terms are conservative as demonstrated by operating experience that has included failed fuel, but it may be too conservative leading to over-designed shielding for normal operations as an example. Design basis source term methodologies for normal operations had not advanced until EPRI published in 2015 an updated ANSI/ANS 18.1 source term basis document. Our paper revisits the fission product appearance rate coefficients as applied in the derivation source terms following the original U.S. NRC NUREG-0017 methodology. New coefficients have been calculated based on recent EPRI results which demonstrate the conservatism in nuclear power plant shielding design.
© The Authors, published by EDP Sciences, 2017
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