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Modeling of the Radiation Doses during Dismantling of RBMK-1500 Reactor Pressurized Tanks from Emergency Core Cooling System

DOI: 10.1155/2013/576432

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Abstract:

Decommissioning of the Ignalina Nuclear Power Plant involves multiple problems. One of them is personnel radiation safety during the performance of dismantling activities. In this paper, modeling results of radiation doses during the dismantling of the pressurized tank from the emergency core cooling system (ECCS PT) of RBMK-1500 reactor are presented. The radiological surveys indicate that the inner surface of the ECCS PT is contaminated with radioactive products of corrosion and sediments due to the radioactive water. The effective doses to the workers have been modeled for different strategies of ECCS PT dismantling. In order to select the optimal personnel radiation safety, the modeling has been performed by the means of computer code “VISIPLAN 3D ALARA Planning tool” developed by SCK CEN (Belgium). The impacts of dismantling tools, shielding types, and extract ventilation flow rate on effective doses during the dismantling of ECCS PT have been analyzed. The total effective personnel doses have been obtained by summarizing the effective personnel doses from various sources of exposure, that is, direct radiation from radioactive equipment, internal radiation due to inhalation of radioactive aerosols, and direct radiation from radioactive aerosols arising during hot cutting in premises. The uncertainty of the collective doses is also presented in this paper. 1. Introduction Ignalina NPP is the only nuclear power plant in Lithuania. Ignalina NPP operated two similar RBMK-1500 units with installed capacity of 1500?MW (each). They were commissioned in 1983 and 1987, and the original design lifetime was projected up to 2010 and 2015, respectively. However, the first unit was shut down at the end of 2004, and the second one was shut down at the end of 2009. The Lithuanian Government approved an immediate decommissioning strategy for the first unit of INPP [1, 2]. Building 117/1, where the emergency core cooling system (ECCS) is installed, is the first dismantling project at Ignalina NPP. After the shutdown of the first unit of INPP, the high pressure part of ECCS pressurized tanks (PT), big diameter pipes, fast acting valves, and the Helium Make-up Station became redundant and were no longer needed for safety or operational purposes and hence could be progressively dismantled. Contamination of internal surfaces of some equipment (big diameter pipes, small pipes, and ECCS PT) that had been in contact with the reactor core cooling water was detected [3]. Nowadays, due to enhancements in computer systems, the dismantling activities are planned using various

References

[1]  The Republic of Lithuania Parliament Decision No. IX-1130, “On Approval of National Energy Strategy,” State news, No. 99-4397, October 2002.
[2]  The Republic of Lithuania Government Resolution No. 1848, “On State Enterprise Ignalina NPP First Unit Decommissioning Concept,” State news, No. 114-5095, November 2002.
[3]  Environment Impact Assessment Report, Ignalina NPP Building 117/1 Equipment Decontamination and Dismantling, VT Nuclear Services Ltd. and Lithuanian Energy Institute (Nuclear Engineering Laboratory), 2008.
[4]  F. Vermeersch, Visiplan 3D Alara Planning Tool, User’s guide, SCK CEN, Mol, Belgium, 2005.
[5]  M. Panik and M. Zachar, “Dose assessment of personnel handling conditioned radioactive waste,” in Proceedings of the 12th International Conference on Environment Remediation and Radioactive Waste Management (ICEM '09), Liverpool, UK, October 2009.
[6]  P. Tatransky and V. Ne?as, “Conditional release of materials from decommissioning process into the environment in the form of steel railway tracks,” Nuclear Engineering and Design, vol. 239, no. 6, pp. 1155–1161, 2009.
[7]  J. Pritrsky and F. Ondra, “Impact of the alternative fuel cycles on the long term safety of deep geological repository,” in Proceedings of the 16th symposium of AER on VVER Reactor Physics and Reactor Safety, Bratislava, Slovakia, September 2006.
[8]  “Gas Safe Ltd. in association with BOC,” http://www.gassafegear.co.uk.
[9]  M. A. Ebadian and S. K. Dua, “Size distribution and rate of production of airborne particulate matter generated during metal cutting,” Final Report, HCET, New Port Richey, Fla, USA, 2001.
[10]  International Commission on Radiological Protection (ICRP 51), “Data for use in protection against external radiation,” A Report of A TAsk Group of Committee 3 of the ICRP, Annals of the ICRP, 1987.
[11]  IAEA Safety Guide, No. RS-G-1.2, Assessment of Occupational Exposure due to Intakes of Radionuclides, IAEA Safety Guide, No. RS-G-1.2, Vienna, Austria, 1999.
[12]  External Exposure to Radionuclides in Air, Water, sand Soil, Federal Guidance Report No. 12, USA, 1993.
[13]  V. Remeikis, A. Plukis, L. Juodis et al., “Study of the nuclide inventory of operational radioactive waste for the RBMK-1500 reactor,” Nuclear Engineering and Design, vol. 239, no. 4, pp. 813–818, 2009.
[14]  Lithuanian Hygiene Standard HN 73, “Basic Standard of Radiation Protection,” The Minister of Health Care, State news, No. 11-388, December 2001.

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