Analysis of AP1000 radioactive material release accidents with MELCOR Accident Consequence Code System (MACCS)

• Autorzy: Niewiński G. , Stępień M. , Góral K.
• Języki publikacji: EN

Abstrakty

EN

The probable introduction in the medium term of nuclear energy into the Polish national power system has become a source of anxiety in society. While Poland already has a research nuclear reactor (acronym: MARIA) at the National Center for Nuclear Research in Świerk, near Warsaw, issues regarding safety and the possible consequences of an accident in the first baseload nuclear power plant have triggered public debate. As part of the licensing process of any newly designed reactor, scenarios for a range of accidents at the plant together with their consequences must be modeled, analyzed and presented in the licensing documentation. In this context a model was built based on a complex set of data - including data provided by the reactor manufacturer, location and environmental data, weather conditions and possible accident scenarios to perform simulations with a computational tool called MELCOR Accident Consequence Code System (MACCS). MACCS is used to perform accident-related calculations, including release of radioactive material to the atmosphere and short and longterm consequences. The analysis involved releases of radioactive material from an AP1000 nuclear reactor assumed to be located on the Polish seacoast and demonstrates that the lethality and incidence of cancer caused by radioactive release are significantly lower than natural.

Słowa kluczowe

EN

MACCS; MELCOR; nuclear reactor; nuclear accident; release of radioactive materials; radioactivity; Gauss plume model

PL

MACCS; MELCOR; reaktor jądrowy; wypadek jądrowy; uwalnianie materiałów radioaktywnych; radioaktywność; model smugi Gaussa

• Wydawca: Institute of Heat Engineering, Warsaw University of Technology
• Czasopismo: Journal of Power Technologies
• Rocznik: 2017
• Tom: Vol. 97, nr 5
• Strony: 446--454
• Opis fizyczny: Bibliogr. 7 poz., rys., tab., wykr.

Twórcy

autor

Niewiński G.

• Institute of Heat Engineering, Warsaw University of Technology, Nowowiejska 21/25, 00-665, Poland

autor

Stępień M.

• Institute of Heat Engineering, Warsaw University of Technology, Nowowiejska 21/25, 00-665, Poland

autor

Góral K.

• Institute of Heat Engineering, Warsaw University of Technology, Nowowiejska 21/25, 00-665, Poland

Bibliografia

• [1] NNB Generation Company LTD: Hinkley point C pre construction safety report: Sub chapter 15.4 Level 2 PSA. London, 2012.
• [2] Ministry of the Environment website, [online], [access: 7th July 2015].
• [3] H. Jow, J. Sprung, L. Ritchie, J. Rollstin, D. Chanin, Melcor accident consequence code system (maccs) model description, Tech. rep., Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; Sandia National Labs., Albuquerque, NM (USA) (1990).
• [4] Burton, R.R.: The Atmospheric Dispersion course notes. Institute of Armospheric Science, School of Earth and Environment, [online], [access: 7th July 2015] <http://homepages.see.leeds.ac.uk/ lecrrb/dispersion/>.
• [5] Westinghouse AP1000 Design Control Document Rev. 19 - Tier 2 Chapter 15 - Accident Analyses - Appendix 15A, [online], [access: 23rd april 2017].
• [6] Sandia National Laboratories: MELCOR Accident Consequence Code System (MACCS) - Model Description. February 1990. [online], [access: 13th april 2017] <https://www.nrc.gov/docs/ML0635/ML063560409.pdf.>.
• [7] B. Wojtyniak, P. Goryński, et al., Sytuacja zdrowotna ludności Polski, Narodowy Instytut Zdrowia Publicznego-Państwowy Zakład Higieny Warszawa, 2016.

Uwagi

PL

Opracowanie rekordu w ramach umowy 509/P-DUN/2018 ze środków MNiSW przeznaczonych na działalność upowszechniającą naukę (2018).