Prediction of External Exposure during Dismantling of Steam Generator


The decommissioning of nuclear power plants is in the Slovak Republic an actual issue. In 2015 started the second decommissioning stage of nuclear power plant V1 in Jaslovské Bohunice. This stage involves the dismantling and segmentation of activated (reactor pressure vessel, reactor internals) and contaminated parts (steam generators, pressurizer). From this reason it is necessary to investigate the radiation situation in the vicinity of the component to be cut. The presented results show that during remote dismantling the exposure is small (compared with the fragmentation tasks). Moreover, when the pre-dismantling decontamination with decontamination factor of 100 is applied, the total collective effective dose is below the yearly limit of 20 mSv for workers.

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Hornáček, M. and Nečas, V. (2015) Prediction of External Exposure during Dismantling of Steam Generator. World Journal of Engineering and Technology, 3, 155-162. doi: 10.4236/wjet.2015.33C023.

Conflicts of Interest

The authors declare no conflicts of interest.


[1] Organisation for Economic Co-Operation and Development—Nuclear Energy Agency. Radioactive Waste Management Committee (2012) The Management of Large Components from Decommissioning to Storage and Disposal: A report of the Task Group on Large Components of the NEA Working Party on Decommissioning and Dismantling (WPDD). NEA/RWM/R(2012)8. Paris: OECD/NEA.
[2] National Nuclear Found for Decommissioning of Nuclear Installations and for Spent Fuel and Radioactive Waste Management (2012) Strategy of Back-end of Peaceful Use of Nuclear Energy in Slovak Republic. (In Slovak)
[3] Nuclear and Decommissioning Company (2013) The Intent in terms of the Act No. 24/2006 Coll. on Environmental Impacts Assessment and Alternations and Amendments of certain Acts as Amended—The 2nd Stage of Decommissiong of V1 NPP Jaslovské Bohunice. (In Slovak)
[4] Roupec, P. (2010) Transfer Heat Analysis in Steam Generators in Blocks of VVER 440. Master’s thesis, Energy Institute, Faculty of Mechanical Engineering, Brno University of Technology. (In Czech)
[5] International Atomic Energy Agency (1997) Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: Steam generators. IAEA-TECDOC-981. ISSN 1011-4289, pp. 15-17.
[6] Vermeersch, F. (2005) Dose Assessment and ALARA Calculation with VISIPLAN 3D ALARA Planning Tool, Training Course. IDPBW Nuclear Studies, Boeretang: SCK.CEN, Belgium.
[7] Rohde, M. (2011) Treatment and Conditioning of Dismantled Material and Oper-ation Waste in EWN, Overview.
[8] Personal and via E-Mail Con-sultation with Mr. Andreas Hammel from the Company WIKUS within the Seminar “Fachtagung Rückbau—Fachtagung zur Technik und Praxis des Rückbaus von Kernkraftwerken” organised by Kraftwerksschule e.v. in NPP Zwentendorf, Austria, from 24-25 September 2014.
[9] Hornacek, M. and Necas, V. (2015) The Assessment of NPP V1 Steam Generator Dismantling from the Perspective of External Exposure. Proceedings of International Conference ECED 2015—Eastern and Central European Decommissioning, 23-25 June 2015, Trnava, Slovakia.
[10] Topf, Ch., Belda, L.S., Fischer, M., Tscheschlok, K. and Volkmann, Ch. (2013) Full System Decontamination at German Nuclear Power Plant Unterweser. International Journal for Nuclear Power, 58, 216-220.

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