Modelling of the Radiological Contamination of the RBMK-1500 Reactor Control and Protection System Channels’ Cooling Circuit ()
Gintautas Poskas1,2,
Rimantas Zujus1
1Nuclear Engineering Laboratory, Lithuanian Energy Institute, Kaunas, Lithuania.
2Department of Thermal and Nuclear Energy, Kaunas University of Technology, Kaunas, Lithuania.
DOI: 10.4236/wjet.2015.33C001
PDF HTML XML
2,847
Downloads
3,422
Views
Citations
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.
Share and Cite:
Poskas, G. and 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.
Conflicts of Interest
The authors declare no conflicts of interest.
References
[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. http://dx.doi.org/10.1533/9780857095336
|
[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. http://dx.doi.org/10.1016/S0022-3115(02)01588-X
|
[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.
|