Abstract
A method of calculating the radiation characteristics of irradiated graphite masonry of an RBMK reactor is described. The MCNP computer code is used to determine the spatial distribution of the neutron flux density in the interior volume of the graphite, the CHAIN code is used to determine the isotopic composition and the radition characteristics of the irradiated graphite on the basis of the MCNP fluxes.
The results of the calculation of the radiation characteristics of graphite from the reactors in the Nos. 2 and 3 units of the Leningrad nuclear power plant and the No. 1 unit of the Chernobyl nuclear power plant are presented and the contribution made by the accident to the flow of fuel mass into the masonry is estimated.
Similar content being viewed by others
REFERENCES
B. K. Bylkin, V. A. Shaposhnikov, V. G. Romanov, et al., “Strategy for the decommissioning of the No. 1 unit of the Leningrad nuclear power plant,” Izv. Akad. Prom. Ékol., No. 1, 67–81 (2001).
B. K. Bylkin, G. B. Davydova, A. V. Krayushkin, et al., “Induced radioactivity and waste classification of reactor zone components of the Chernobyl nuclear power plant unit 1 after the final shutdown,” Nucl. Techn., 136, No. 1, 76–88 (2001).
J. Breismeister, MCNP 4A - Monte Carlo N-Particle Transport Code System, LA-12625-M (1993).
A. V. Bushuev, Yu. M. Verzilov, V. N. Zubarev, et al., “Determination of the 3 H and 14 C content in reactor graphite,” At. Énerg., 73, No. 6, 446–450 (1992).
B. K. Bylkin, G. B. Davydova, A. V. Krayushkin, et al., “Computational analysis of the radiation characteristics of the structure of the reactor in the No. 1 unit at the Chernobyl nuclear power plant after final shutdown,” in: Abstracts of the Reports of a Conference at International Chernobyl Center, Slavutich, Ukraine, October 13- 16, 1999, p. 4.
Author information
Authors and Affiliations
Rights and permissions
About this article
Cite this article
Bylkin, B.K., Davydova, G.B., Krayushkin, A.V. et al. Computational Estimates of the Radiation Characteristics of Irradiated Graphite after Final Shutdown of a Nuclear Power Plant with an RBMK Reactor. Atomic Energy 96, 411–416 (2004). https://doi.org/10.1023/B:ATEN.0000041209.73666.36
Issue Date:
DOI: https://doi.org/10.1023/B:ATEN.0000041209.73666.36