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2017 | 131 | 3 | 514-518
Article title

Role of Operational Radioprotection Simulation in the Dismantling of the Protection and Control Rods of VVR-S Reactor

Content
Title variants
Languages of publication
EN
Abstracts
EN
The VVR-S nuclear research reactor owned by Horia Hubulei National Institute of Physics and Nuclear Engineering, has functioned between 1957 and 1997 at a nominal thermal power of 2 MW, using less-enriched nuclear fuel (10%), type EK-10, and highly enriched fuel (36%), type S-36. The reactor control was carried out by means of nine rods placed in the central part of the core. Four rods were used for the manual control of power, one for automatic control, three rods for reactor safety (emergency rods) and one for the fine control of power. One of the high hazard operations was the dismantling of the activated-contaminated control rods. Because of a higher radiological risk, simulation was performed to determine the expected maximum dose. The maximum gamma dose rate obtained using simulated results was 3.5 Sv/h, for the highly activated rod. In the real measurement, when the work was performed, the maximum gamma dose rate was 3 Sv/h. ⁹⁰Sr+⁹⁰Y are expected to be present in the control rods radioactivity.
Keywords
EN
Year
Volume
131
Issue
3
Pages
514-518
Physical description
Dates
published
2017-03
References
  • [1] Plan de Dezafectare al Reactorului Nuclear de Cercetare VVR-S (Decommissioning Plan of the VVR-S Research Reactor), M. Dragusin, V. Copaciu, V. Popa, C. Dragolici, I. Iorga, R. Deju, C. Mustata, C. Tuca, I. Mincu, ROM 04 029/2003, applicable revision
  • [2] VVR-S RFS Reactor - VVR-S - Reactor Final Security Report
  • [3] http://www.jakeman.com.au/media/as-high-or-low-as-reasonably-practicable-ahlarp or http://www.31000risk.blogspot.com/{www.31000risk.blogspot.com/
  • [4] M. Dragusin, A.O. Pavelescu, I. Iorga, Nucl. Technol. Radiat. Protect. 26, 1451 (2011)
  • [5] IAEA Nuclear Energy Series No. NW-G-2.1, Policies and Strategies for the Decommissioning of Nuclear and Radiological Facilities, International Atomic Energy Agency, Vienna 2011
  • [6] Technical Reports Series No. 446, Decommissioning of Research Reactors: Evolution, State of the Art, Open Issues, International Atomic Energy Agency Vienna 2006
  • [7] Technical Reports Series No. 463, Decommissioning of Research Reactors and Other Small Facilities by Making Optimal Use of Available Resources, International Atomic Energy Agency, Vienna 2008
  • [8] IAEA-TECDOC-1394 Planning, managing and organizing the decommissioning of nuclear facilities: lessons learned, International Atomic Energy Agency, Vienna 2004
  • [9] M. Dragusin, R. Deju, V. Popa, I. Iorga, Decommissioning of the Nuclear Research Reactor VVR-S Magurele Bucharest Romania, (1 Sept. 2011) http://www.iaea.org/OurWork/ST/NE/NEFW/WTS-Networks/IDN/idnfiles/Presentations-in-pdf-Necsa/Country_presentations/Romania.pdf
  • [10] Normele Fundamentale de Securitate Radiologica - Fundamental Norms on Radiological Safety (NSR-01), CNCAN, Bucuresti 2002
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  • [12] IAEA Nuclear Energy Series No. NW-T-1.18, Determination and Use of Scaling Factors for Waste Characterization in Nuclear Power Plants, International Atomic Energy Agency, Vienna 2009
Document Type
Publication order reference
YADDA identifier
bwmeta1.element.bwnjournal-article-appv131n350kz
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