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Calculation of external exposure during dismantling and segmentation of steam generator

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Warianty tytułu
PL
Obliczenia ekspozycji zewnętrznej podczas demontażu i segmentacji generatora pary
Języki publikacji
EN
Abstrakty
EN
The prediction of radiation doses obtained during dismantling of steam generator represents one of the most crucial issues within the process of decommissioning of nuclear installations. Given the fact that in Slovakia the nuclear power plant VI in Jaslovské Bohunice is currently being decommissioned, represents the analysis of the segmentation of steam generator an actual issue. In this paper, the proposed dismantling methodology together with the results of calculations is given. Also the complex analysis of the influence of different distance of workers carrying out the dismantling as well as the influence of the time on the total collective effective dose is carried out. The results of this analysis show that the obtained doses are below the legislative limits and thus the main consequences can be applied in the process of VI nuclear power plant decommissioning.
PL
Przewidywanie dawek promieniowania na które narażona jest obsługa w trakcie demontażu generatora pary reprezentuje jedną z najbardziej kluczowych problemów w ramach procesu likwidacji obiektów jądrowych. Mając na względzie fakt, że na Słowacji elektrownia jądrowa VI w Jaslovské Bohunice jest obecnie wycofywana z ruchu, analiza segmentacji generatora pary stanowi aktualny problem. W pracy zaproponowano metodologię demontażu i podano rezultaty obliczeń. Także złożona analiza wpływu różnych odległości pracowników przeprowadzających demontaż jak również wpływ czasu na całkowitą efektywną zespołową dawkę promieniowania jest przeprowadzony. Wyniki tej analizy pokazują że przyjęte dawki są poniżej limitów wyznaczonych normami i zatem główne konsekwencje mogą być stosowane w procesie demontażu jądrowej elektrowni VI.
Rocznik
Tom
Strony
3--10
Opis fizyczny
Bibliogr. 32 poz., rys., tab., wykr.
Twórcy
autor
  • Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Institute of Nuclear and Physical Engineering
autor
  • Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Institute of Nuclear and Physical Engineering
Bibliografia
  • [1] Bach F-W., Dufaud J-M., Lorin Ch.: Dismantling and Segmentation. EUR 16211 - Handbook on decommissioning of nuclear installations. Luxembourg: Office for Official Publications of the European Communities, 1995.
  • [2] Barabáš K.: Nuclear power plants. Faculty of Electrical Engineering, Czech Technical University in Prague, 1985 (in Czech).
  • [3] Bauerfeind M., Feinhals J.: The Disposal of Large Components Strategies. [online].Available: <http://www.iaea.org/OurWork/ST/NE/NEFW/IDN/Feinhals%20-%202.pdf>.
  • [4] Beverungen M.: External Disposal of 4 Steam Generators out of the Decommissioning of the Nuclear Power Plant Stade (KKS). International Conference on Environmental Remediation and Radioactive Waste Management ICEM 2009, Liverpool, United Kingdom, October 11-15, 2009. ASME, 2009.
  • [5] Borchardt R.: Dismantling of the Reactors on the Greifswald Nuclear Power Plant (KGR) Site. [online]. Available: <http://www.iaea.org/OurWork/ST/NE/NEFW/WTSNetworks/IDN/idnfiles/CuttingTechniqueWkpGermany2011/EWN_Dismantling_of_the_reactors_on_the_Greifswald_Nuclear_Power_Plant_site.pdf>
  • [6] Borchardt R.: Transport of the Reactor Pressure Vessels in the Greifswald Nuclear Power Plant. International Conference on Environmental Remediation and Radioactive Waste Management ICEM 2009, Liverpool, United Kingdom, October 11-15, 2009. ASME, 2009.
  • [7] Federal Ministry for the Environment, Nature Conservation and Nuclear Safety. Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management: Report of the Federal Republic of Germany for the fourth Review Meeting in May 2012. [online]. Available: <http://www.bmu.de/fileadmin/bmuimport/files/english/pdf/application/pdf/jc_4_bericht_deutschland_en.pdf>.
  • [8] Geiger H., Schymke K.: Weltweite Logistik im gesamten Nuklear-Kreislauf: Nuclear Cargo + Service GmbH. International Journal for Nuclear Power, vol. 56, no. 3, 2011, 169-170.
  • [9] Ghandour A.: Duratek Transports Reactor Pressure Vessel to Barnwell. [online]. Available: <http://media.corporateir.net/media_files/NSD/DRTK/reports/insite/34/rpv.html>.
  • [10] Hornáček M., Nečas V.: The Analysis of the Process of Dismantling of Large Components used in Nuclear Power Plants from the Perspective of Radioactive Waste Disposal. Regional Seminar on Radioactive Waste Disposal, Senec, Slovakia, October 8 – 9, 2013. DECOM, a.s. Trnava, 2013.
  • [11] Hrnčíř T., Nečas V.: Recycling and reuse of very low level radioactive steel in motorway tunnel scenario. Nuclear Engineering and Design, 265/2013, 534-541.
  • [12] Hrnčíř T., Pánik M., Ondra F., Nečas V.: The impact of radioactive steel recycling on the public and professionals. Journal of Hazardous Materials, 254- 255, 2013, 98-106.
  • [13] International Atomic Energy Agency. Assessment and management of ageing of major nuclear power plant components important to safety: Steam generators, IAEA-TECDOC-981. Vienna, IAEA, 1997.
  • [14] International Atomic Energy Agency. Radiological Characterization of Shut Down Nuclear Reactors for Decommissioning Purposes – Technical Reports Series No. 389. Vienna, IAEA, 1998.
  • [15] Knaack M.: Dismantling of Large Components. [online]. Available: <http://www.iaea.org/OurWork/ST/NE/NEFW/WTSNetworks/IDN/idnfiles/WkpPlanLicencingDecomProjetc_Germany2012/WkpPl anLicencingDecomProjetc_Germany2012-Dismantling_Large_ComponentsKnaack.pdf>.
  • [16] Loeb A., Stanke D., Kemp L.: Decommissioning of the reactor pressure vessel and its peripheral facilities of the Nuclear Power Plant in Stade, Germany – 11100. WM2011 Conference, Phoenix, Arizona, USA, February 27 – March 3, 2011.
  • [17] Loeb A.: RDB Rückbau im Kernkraftwerk Stade: Innovative Umsetzung. International Journal for Nuclear Power, vol. 56, no. 3, 2011, 171-175.
  • [18] National Nuclear Found for Decommissioning of Nuclear Installations and for Spent Fuel and Radioactive Waste Management. Strategy of Back-end of Peaceful Use of Nuclear Energy in Slovak Republic, 2012 (in Slovak).
  • [19] Nuclear and Decommissioning Company. 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. [online]. Available: <http://www.javys.sk/sk/ospolocnosti/projekty/posudenie-vplyvu-2-etapy-vyradovania-je-v1-nazp/dokumenty> (in Slovak).
  • [20] Organization for Economic Co-operation and Development – Nuclear Energy Agency. Radioactive Waste Management Committee, 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, (2012), OECD/NEA.
  • [21] Philipp M.: Die Energiewerke Nord GmbH – Der Weg vom Betreiber eines stillgelegten russischen Kernkraftwerkes zu einem führenden Stilllegungsunternehmen in Europa. International Journal for Nuclear Power, vol. 56, no. 3, 2011, 160-164.
  • [22] Rohde M.: Treatment and Conditioning of Dismantled Material and Operation Waste in EWN, Overview. [online]. Available: <http://www.iaea.org/OurWork/ST/NE/NEFW/WTSNetworks/IDN/idnfiles/CuttingTechniqueWkp-Germany2011/Treatment-andConditioning-of-DismantledMaterial-and-OperationWaste.pdf>
  • [23] Roupec P.: Transfer Heat Analysis in Steam Generators in Blocks of VVER 440. Master’s thesis, Energy Institute, Faculty of Mechanical Engineering, Brno University of Technology, 2010 (in Czech).
  • [24] Statutory Order No. 345/2006 on the Basic Safety Requirements on Personnel and Public Health Protection against Ionizing Radiation (in Slovak). Government of Slovak Republic, 2006.
  • [25] Steiner H., Eickelpasch N., Tegethoff H.: Experience with the dismantling of three secondary steam generators in unit A Gundremmingen by the ‘ice sawing‘ technique. Nuclear Engineering and Design, vol. 170, 1997, 165-173.
  • [26] Stiepani Ch.: Full System Decontamination (FSD) prior to Decommissioning. Proceedings of the ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management ICEM2011, Reims, France, September 25-29, 2011. ASME, 2009.
  • [27] Tatranský P., Nečas V.: Conditional release of materials from decommissioning process into the environment in the form of steel railway tracks. Nuclear Engineering and Design, 239, 2009, 1155-1161.
  • [28] Topf Ch., Belda L. S., Fischer M., Tscheschlok K., Volkmann Ch.: Full System Decontamination at German Nuclear Power Plant Unterweser. International Journal for Nuclear Power, atw Vol. 58, 2013, 216-220.
  • [29] Vermeersch F.: Dose Assessment and ALARA Calculation with VISIPLAN 3D ALARA Planning tool. Training Course, IDPBW Nuclear Studies, Boeretang: SCK.CEN, Belgium, 2005.
  • [30] Walberg M., Viermann J., Beverungen M., Kemp L., Lindström A.: Disposal of Steam Generators from Decommissioning of PWR Nuclear Power Plants. IYNC 2008, Interlaken, Switzerland, 20-26 September 2008, 158.1-158.10.
  • [31] Weil L., Rehs B.: Nuclear Power Plant Decommissioning in Germany – Projects, Regulation and Experience. International Conference on Environmental Remediation and Radioactive waste management ICEM 2009, Liverpool, United Kingdom, October 11-15, 2009. ASME, 2009.
  • [32] Wheeler D. M.: Large Component Removal/Disposal. WM’02 Conference, Tucson, Arizona, USA, February 24-28, 2002. [online]. Available: <http://www.wmsym.org/archives/2002/Proceedings/44/573.pdf>.
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-5fcb8256-c8b8-4f49-9854-c1f9e9ca0bb1
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