WJET  Vol.3 No.3 C , October 2015
Modelling of the Radiological Contamination of the RBMK-1500 Reactor Control and Protection System Channels’ Cooling Circuit
Abstract: The article presents results of modelling and analysis of component contamination of the RBMK- 1500 reactor Control and Protection System channels’ Cooling Circuit (CPSCC) at Ignalina NPP Unit 1. The modelling was performed using a computer code LLWAA-DECOM (Tractebel Energy Engineering, Belgium), taking into consideration CPSCC components characteristics, parameters of the water flowing in the circuits, system work regimes, etc. During the modelling, results on activity of CPSCC components’ deposits, nuclide composition of the deposits and dose rates after the final shutdown of the reactor, as well as activity decay of the most contaminated CPSCC components’ deposits were obtained. Analysis showed that there is a significant difference in contamination levels between CPSCC components. The rundown header from the channels of the reactor’s fast acting scram system is the most contaminated component, and contamination of the least contaminated component is only 0.27% compared to the activity of the most contaminated component. Corrosion nuclides are the nuclides that mostly contribute to contamination of the CPSCC deposits.
Cite this paper: Poskas, G. , Zujus, R. (2015) Modelling of the Radiological Contamination of the RBMK-1500 Reactor Control and Protection System Channels’ Cooling Circuit. World Journal of Engineering and Technology, 3, 1-5. doi: 10.4236/wjet.2015.33C001.

[1]   (1998) Radiological Characterization of Shut down Nuclear Reactors for Decommissioning Purposes. Technical Reports Series No. 389, IAEA, Vienna, 184 p.

[2]   (2012) Modelling of Transport of Radioactive Substances in the Primary Circuit of Water-Cooled Reactors. Technical Reports Series No. 1672, IAEA, Vienna, 149 p.

[3]   You, D., Lam-bert, J. and Feron, D. (1996) Dissolution and Solubility of Cobalt and Nickel Ferrites in PWR Primary Conditions. 7th International Conference on Water Chemistry of Nuclear Reactors Systems, Bournemouth.

[4]   Kritsky, V.G. (1996) Water Chemistry and Corrosion of NPP Structural Materials, Sinto.

[5]   (1993) Coolant Technology of Water Cooled Reactors: An Overview. Technical Reports Series No. 347, IAEA, Vienna.

[6]   Laraia, M. (2012) Nuclear Decommissioning: Planning, Execution and International Experience. Woodhead Publishing Series in Energy, No. 36, 824.

[7]   Lewis, B.J. and Husain, A. (2003) Modelling the Activity of I129 in the Primary Coolant of a CANDU Reactor. Journal of Nuclear Materials, 312, 81-96.

[8]   Almenas, K., Kaliatka, A. and Uspuras, E. (1998) Ignalina RBMK-1500. A Source Book. Ignalina Safety Analysis Group, 200 p.

[9]   Lemens, A., Centner, B.B., Beguin, P. and Mannaerts, K. (1999) Determination and Declaration of Critical Nuclide Inventories in Belgian NPP Radwaste Streams. Proceedings of WM’99 Conference, 28 February-4 March 1999, Manule de conception du programme de calcul de l’activedans depots des equipments des centrals de Doelet Tihange.