Questions pertaining to the development of reactors from the standpoint of the evolution of protection and emergency response systems for large radiation accidents, and development of probabilistic safety analysis at different levels are examined. Examples are presented of the calculation of quantitative characteristics of risk in an accident at a model NPP that show the possibility of using VAB-3 to evaluate the scale of countermeasures as a function of the level of intervention, their effectiveness as a function of the time of application and validation of countermeasures for an individual populated point. It is shown that the VAB-3 methodology must be developed in order to increase NPP safety.
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References
A. P. Aleksandrov, Nuclear Power and Scientific-Technical Progress, Moscow (1978).
S. V. Onufrienko, V. V. Bezlenkin, and S. E. Semashko, “Particularities of the concept of AES-2006 design safety on the LAES-2 site,” Tyazh. Mash., No. 2, 6–10 (2008).
NP-001–2015, General Tenets of the Safety Security of Nuclear Power Plants, Ruling No. 522 of the Federal Office of Environmental, Technological, and Nuclear Oversight, Dec. 17, 2015.
R. M. Aleksakhin, L. A. Buldakov, V. A. Gubanov, et al., Radiation Accidents, L. A. Il’in and V. A. Gubanov (eds.), IzdAT, Moscow (2001).
The Accident at the Fukushima-1 NPP: Response Experience and Lessons, in: Proc. IBRAE RAN, Nauka, Moscow (2013), Iss. 13.
A. M. Aganov and G. A. Novikov, Nuclear and Radiological Safety Culture: Government Guarantees, Ideology, Principles, and Implementation Methods, Atomprof, St. Petersburg (2010).
R. V. Arutyunyan, S. N. Krasnoperov, and M. D. Segal’, “Analysis of the reasons for scaling of socio-economic consequences of radiation accidents,” Probl. Bezop. Chrezv. Sit., No. 2, 112–117 (2009).
R. V. Arutyunyan, S. N. Krasnoperov, I. A. Osip’yan, and M. D. Segal’, “Scientific-technical and expert support of decision making during accidents with the radiation factor,” Probl. Bezop. Chrezv. Sit., No. 2, 23–28 (2010).
Safety Culture, Safety Series No. 75 INSAG-4, IAEA, Vienna (1991).
A. P. Panfilov, “Evolution of systems supporting radiation safety of the nuclear industry in a country and its current status,” ANRI, No. 1(84), 2–15 (2016).
“Declaration about policy on application of probabilistic safety analysis and risk-informed methods for nuclear power plants,” Yad. Rad. Bezop., No. 1, 41–45 (2012).
RB-032–04, Basic Recommendations on Performing Probabilistic Safety Analysis of Nuclear Power Plants, Ruling No. 3 of the Federal Office of Nuclear Oversight, April 21, 2004.
Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 3): Off-Site Consequences and Estimation of Risks to the Population, Safe Ser. No. 50-P-12, IAEA, Vienna (1996).
R. V. Arutyunyan, V. A. Panteleev, and M. D. Segal’, “Status of the development of level 3 probabilistic safety analysis (VAB-3) four objects utilizing atomic energy,” Probl. Bezop. Chrezv. Sit., No. 2, 49–57 (2016).
R. V. Arutyunyan, V. A. Panteleev, M. D. Segal’, et al., “On the significance of the development of methodological apparatus of level 3 probabilistic safety analysis (VAB-3) for objects utilizing atomic energy,” Probl. Bezop. Chrezv. Sit., No. 2, 91–99 (2015).
Use and Development of Probabilistic Safety Assessment. An Overview of the Situation at the End of 2010, NEA/CSNI (2013).
Safety Assessment and Independent Verification for Nuclear Power Plants, No. NS-G-1.2, IAEA, Vienna (2004).
RD 03-418–01, Methodological Guidelines for Performing Risk Analysis of Dangerous Industrial Objects, Federal Mining and Industrial Oversight of Russia, Ruling No. 30 of Gosgortekhnadzor Rossii, July 10, 2001.
M. V. Lisanov, K. V. Efremov, V. A. Panteleev, and S. I. Sumskoi, “Comparison of the computational results for consequences of accidental emissions of dangerous substances according to the software systems TOKSI+ and PHAST,” Bezop. Truda Prom., No 2, 56–60 (2011).
Reactor Safety Study – an Assessment of Accident Risks in US Commercial Nuclear Power Plants, WASH1400, USNRC, Oct. 1975.
R. V. Arutyunyan, L. A. Bol’shov, D. A. Pripachkin, et al., “Assessment of radionuclide emission during the Fukushima-1 NPP accident (Japan) on March 15, 2011,” At. Energ., 112, No. 3, 159–163 (2012).
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Translated from Atomnaya Énergiya, Vol. 123, No. 6, pp. 344–349, December, 2017.
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Arutyunyan, R.V., Panteleev, V.A., Segal’, M.D. et al. Level-3 Probabilistic Safety Analysis VAB-3 as an NPP Safety Enhancement Stage. At Energy 123, 418–423 (2018). https://doi.org/10.1007/s10512-018-0362-0
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DOI: https://doi.org/10.1007/s10512-018-0362-0