Analysis of the Human Biohazard of Long-Lived Fission Products and Actinides for BREST-OD-300 Spent Fuel


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Abstract

The aim of this work is to perform a comparative analysis of the biohazard for the population of long-lived fission products and actinides from BREST-OD-300 reactor spent fuel taking account of the time required for different radionuclides to reach Earth’s surface by migrating from a deep disposal site. It was found that the biohazard of fission products is significantly greater than that of actinides for a long time (20000 years according to the accepted scenario of radionuclide migration). The radiological impact on the population is predicted after 99Tc – radionuclide with high migration capability – reaches the soil surface. 137Cs and 90Sr will not appreciably affect the dose load because of their relatively short half-life. In order to maintain radio-ecological balance between long-lived wastes and native uranium during the entire possible time period, it is sufficient to extract from the BREST-OD-300 spent fuel 90% of the technetium and 75% of the americium with 99.9% of the fissile materials extracted.

About the authors

S. I. Spiridonov

All-Russia Research Institute of Radiology and Agroecology (VNIIRAE)

Email: j-atomicenergy@yandex.ru
Russian Federation, Obninsk

A. N. Perevolotskii

All-Russia Research Institute of Radiology and Agroecology (VNIIRAE)

Email: j-atomicenergy@yandex.ru
Russian Federation, Obninsk

T. V. Perevolotskaya

All-Russia Research Institute of Radiology and Agroecology (VNIIRAE)

Email: j-atomicenergy@yandex.ru
Russian Federation, Obninsk

R. M. Aleksakhin

Innovation-Technology Center for Project Breakthrough (ITTsP Proryv)

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

E. V. Spirin

Innovation-Technology Center for Project Breakthrough (ITTsP Proryv)

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

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