Modeling of 14C Diffusion from the Core of the Decommissioned ad Reactor

• Published in: Atomic energy (New York, N.Y.) Vol. 118; no. 5; pp. 346 - 350
• Main Authors: Antonenko, M. V., Chubreev, D. O., Kuznetsov, G. V.
• Format: Journal Article
• Language: English
• Published: New York Springer US 01-09-2015
• Subjects: Hadrons; Heavy Ions; Nuclear Chemistry; Nuclear Energy; Nuclear Physics; Physics; Physics and Astronomy; Reactor Shaft; Radionuclide; Barrier Material; Radioactive Carbon; Safety Barrier
• ISSN: 1063-4258; 1573-8205
• DOI: 10.1007/s10512-015-0005-7

A mathematical model of the diffusion of radionuclides through engineered safety barriers is developed for
14
C in order to determine the long-term safety conditions and characteristics of a decommissioned commercial uranium-graphite reactor. Dry and wet mixtures and concrete are used as the barrier materials. Diffusion is studied as the dominant mechanism for the transport of the radionuclides. The
14
C concentration at the boundary between the radwaste storage site and the environment is determined computationally and the effect of the modeling conditions on the specific activity of the radionuclide is analyzed. The decomposition sequence of the safety barriers for which the
14
C concentration is much lower than the admissible value is determined.