AN APPLICATION OF IRIDM IN THE DECISION MAKING PROCESS ON FUEL CONVERSION OF THE MARIA REACTOR
Mieczysław Józef Borysiewicz
manhaz@cyf.gov.plNational Centre for Nuclear Research (NCBJ), Nuclear Energy Department, Nuclear Energy Division (Poland)
Karol Kowal
National Centre for Nuclear Research (NCBJ), Nuclear Energy Department, Nuclear Energy Division (Poland)
Piotr Andrzej Prusiński
National Centre for Nuclear Research (NCBJ), Nuclear Energy Department, Nuclear Energy Division (Poland)
Marcin Dąbrowski
National Atomic Energy Agency (NAEA), Department of Nuclear Safety, Division of Inspection of Nuclear Installations (Poland)
Abstract
Poland, when acceded to GTRI (Global Threat Reduction Initiative) in 2004, has committed to convert the nuclear fuel of the Research Reactor MARIA, operated by the National Centre for Nuclear Research (NCBJ) in Świerk. The conversion means giving up of high enriched uranium fuel containing 36% of U-235, which was used so far, and replacing it with the low enriched uranium fuel (19.7% U-235). This article describes the potential usability of the Integrated Risk Informed Decision Making (IRIDM) methodology in optimization of the fuel conversion procedure.
Keywords:
nuclear safety, Integrated Risk Informed Decision Making (IRIDM), Research Reactor MARIA, Global Threat Reduction Initiative (GTRI), nuclear fuel conversionReferences
Borek-Kruszewska E., Mieleszczenko W.: New LEU Fuel in the MARIA Research Reactor. NCBJ Annual Report 2011, pp. 261.
Google Scholar
Borysiewicz M., Kowal K., Prusiński P.A., Dąbrowski M.: An Integrated Risk Informed Decision Making in the Nuclear Industry. Informatics Control Measurement In Economy and Environment Protection 02/2013, in press.
DOI: https://doi.org/10.35784/iapgos.1448
Google Scholar
Dorosz M., Nowakowski P.: Hydraulically measurement to compare fuel elements types MC5 and MR6. IAE Internal Report, Otwock-Świerk 2009.
Google Scholar
Golnik N., Pytel K.: Irradiation Facilities for BNCT at Research. Reactor MARIA in Poland. Polish Journal of Medical Physics and Engineering 12/2006, pp. 143-153.
Google Scholar
Krzysztoszek G., Gołąb A., Jaroszewicz J.: Operation of the Maria Research Reactor, IEA Annual Report 2010, pp. 13-16.
Google Scholar
Krzysztoszek G., Jaroszewicz J., Pytel K.: Irradiations of HEU targets in MARIA RR for Mo-99 production. Proceedings of the 1st International Nuclear Energy Congress, Warszawa 2011.
Google Scholar
Krzysztoszek G., Marcinkowska Z., Pytel K., Hanan N.: Qualification Process of LEU Fuel – CERCA Type and Conversion Planning for MARIA Research Reactor. Proceedings of the International Meeting on Reduced Enrichment for Research and Test Reactors, Santiago 2011, pp. 1-8.
Google Scholar
Krzysztoszek G., Pytel K.: Irradiation of the LEU fuel in MARIA research reactor. Proceedings of the International Meeting on Reduced Enrichment for Research and Test Reactors, Beijing 2009.
Google Scholar
Lyubarskiy A., Kuzmina I., El-Shanawany M.: Advances in Risk Informed Decision Making – IAEA’s Approach. Proceedings of the Nordic PSA Conference, Gottröra 2011, pp. 1-14.
Google Scholar
Marcinkowska Z., Pytel K., Mołdysz A.: Neutronic Calculations for MARIA Core Conversion. NCBJ Annual Report 2011, pp. 250.
Google Scholar
Prusiński P.A., Potempski S., Borysiewicz M., Kowal K., Kwiatkowski T., Prusiński A.M.: CFD analysis of the safety related thermal hydraulic parameters describing a flow domain of an experimental medical installation (BNCT converter) inside of the Research Reactor MARIA. Journal of Power Technologies 4/2012, pp. 227-240.
Google Scholar
International Atomic Energy Agency: Risk informed regulation of nuclear facilities: Overview of the current status. IAEA, Vienna 2005.
Google Scholar
International Atomic Energy Agency: A Framework for an Integrated Risk Informed Decision Making Process. IAEA, Vienna 2011.
Google Scholar
http://nnsa.energy.gov/
Google Scholar
Authors
Mieczysław Józef Borysiewiczmanhaz@cyf.gov.pl
National Centre for Nuclear Research (NCBJ), Nuclear Energy Department, Nuclear Energy Division Poland
Authors
Karol KowalNational Centre for Nuclear Research (NCBJ), Nuclear Energy Department, Nuclear Energy Division Poland
Authors
Piotr Andrzej PrusińskiNational Centre for Nuclear Research (NCBJ), Nuclear Energy Department, Nuclear Energy Division Poland
Authors
Marcin DąbrowskiNational Atomic Energy Agency (NAEA), Department of Nuclear Safety, Division of Inspection of Nuclear Installations Poland
Statistics
Abstract views: 225PDF downloads: 140
License
This work is licensed under a Creative Commons Attribution-ShareAlike 4.0 International License.
Most read articles by the same author(s)
- Karol Kowal, Mieczysław Borysiewicz, RELIABILITY ANALYSIS OF PWR REACTOR PROTECTION SYSTEM , Informatyka, Automatyka, Pomiary w Gospodarce i Ochronie Środowiska: Vol. 5 No. 1 (2015)
- Mieczysław Józef Borysiewicz, Karol Kowal, Piotr Prysiński, Marcin Dąbrowski, AN INTEGRATED RISK INFORMED DECISION MAKING IN THE NUCLEAR INDUSTRY , Informatyka, Automatyka, Pomiary w Gospodarce i Ochronie Środowiska: Vol. 3 No. 2 (2013)
- Tomasz Pikula, Karol Kowal, Piotr Guzdek, FREQUENCY DEPENDENCE OF THE MAGNETOELECTRIC VOLTAGE COEFFICIENT IN (BiFeO3)x-(BaTiO3)1-x CERAMICS , Informatyka, Automatyka, Pomiary w Gospodarce i Ochronie Środowiska: Vol. 5 No. 4 (2015)
- Karol Kowal, Mieczysław Borysiewicz, RELIABILITY ANALYSIS OF EMERGENCY DECAY HEAT REMOVAL IN PWR REACTOR , Informatyka, Automatyka, Pomiary w Gospodarce i Ochronie Środowiska: Vol. 5 No. 3 (2015)
