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  • Kärkelä, T, et al. (creator_code:aut_t)
  • Gas phase reactions of organic iodine in containment conditions
  • 2010
  • record:In_t: International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010. - 9781617386435 ; 2, s. 1084-1091
  • swepub:Mat_conferencepaper_t (swepub:level_scientificother_t)abstract
    • In case of a hypothetical severe accident it is very likely that iodine at least partly deposits on painted walls of a reactor containment building. Iodine may react with painted surfaces to form organic iodine species. These organic species are a possible source of volatile iodine, which may increase the fraction of releasable iodine. Therefore, it is important to study the transport of organic iodine in containment conditions. Another question is, in which form are the organic iodides transported as gaseous molecules or as aerosol particles resulting from organic iodides reacting with radiolysis products. To answer this last question methyl iodide was fed into the EXSI facility in an air mixture. In some experiments the flow contained also humidity. The reactions took place in a quartz tube heated either to 50°C, 90°C or 120°C. UV-light was used as a source of radiation to produce ozone from oxygen. A separate generator was also applied to reach higher ozone concentrations. Nucleated aerosol particles were collected on plane filters and gaseous iodine species were trapped in trapping bottles. Aerosol mass flow rate and size distribution as well as speciation of gaseous reaction products were measured with several on-line instruments. Collected aerosol particles were analysed with SEM. It was found that the formation of aerosol particles was very fast when ozone and methyl iodide were present in the facility. Even a very low concentration of ozone produced high number concentration of particles. The measured aerosol mass concentration increased with increasing temperature and ozone concentration. Because the particle diameter was quite small (
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  • Kärkelä, T, et al. (creator_code:aut_t)
  • Nordic Collaboration: Impact of Ag and NOx Compounds on the Transport of Ruthenium in the Primary Circuit of NPP in a Severe Accident
  • 2016
  • record:In_t: 25th International Conference Nuclear Energy for New Europe, (Nene 2016); proccedings eds. Snoj, L; Lengar, I.. - 9789616207409 ; , s. no. 802-
  • swepub:Mat_conferencepaper_t (swepub:level_refereed_t)abstract
    • When ruthenium is released from the fuel as ruthenium oxides to the environment in a severe NPP accident, ruthenium isotopes Ru-103 and Ru-106 cause a radiotoxic risk to the population both in a short and long term. As the previous international studies on the transport of ruthenium in the reactor coolant system (RCS) have mainly been conducted in pure air-steam atmospheres, the current study was dedicated to air ingress conditions with representative airborne air radiolysis (NOx) and control rod (Ag) species which were mixed with vaporized Ru oxides. The aim was to study the impact of these additives on the transport of ruthenium as gas and particles through the primary circuit of nuclear power plant in a severe accident. As a main outcome, the transport of gaseous ruthenium through the facility increased significantly when the oxidizing NO2 gas was fed into the atmosphere.
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  • Van Dorsselaere, J. -P, et al. (creator_code:aut_t)
  • Status of the SARNET network on severe accidents
  • 2010
  • record:In_t: International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010. - 9781617386435 ; , s. 1029-1043
  • swepub:Mat_conferencepaper_t (swepub:level_refereed_t)abstract
    • After four and a half years of operation in the frame of the 6th Framework Programme (FP6) of the European Commission, SARNET (Severe Accidents Research NETwork of excellence) continues in the FP7 (project named SARNET2) from April 2009 for 4 years. Forty-one organisations from 21 countries network their capacities of research in order to resolve the most important remaining uncertainties and safety issues on severe accidents (SA) in existing and future water-cooled nuclear power plants (NPPs). It includes a large majority of the Europeanactors involved in SA research plus a few non-European important ones. The objective is to perform the common research programmes that have been defined in the network first phase and to continue to improve the common computer tools and methodologies for NPP safety assessment. It will consolidate the sustainable integration of the European SA research capacities. These research programmes concern essentially the six highest priority safety issues that were identified after ranking in the first phase of the network: in-vessel core coolability, molten-corium-concrete-interaction, fuel-coolant interaction, hydrogen mixing and combustion in containment, impact of oxidising conditions on source term, and iodine chemistry. The Joint Programme of Activities includes the following main tasks: Performing new experiments on the above mentioned issues andjointly analysing their results in order to elaborate a common understanding of the concerned physical phenomena; Continuing the development and assessment of the ASTEC integral computer code (jointly developed by IRSN and GRS to predict the NPP behaviour during a postulated SA), which capitalizes in terms of models the knowledge produced in the network. In particular efforts are being extended to its applicability to BWR and CANDU NPP types; Continuing the storage of the SA experimental results in a scientific database, based on the STRESA JRC tool; Promoting educational and training courses, ERMSAR (European Review Meeting on Severe Accident Research) international conferences (to be held once a year) and mobility of young researchers or students between the various European organisations. Some R&D results obtained in the first year of the project are presented, in particular: the VULCANO experiment done in CEA mid-2009 on molten-core-corium-interaction, and the release of the first version of the new ASTEC V2 series.
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