glonucsecГлобальная ядерная безопасностьGlobal Nuclear Safety2305-414X2499-9733National Research Nuclear University "MEPhI"10.26583/GNS-2018-02-02UXASEEglonucsec-472Research ArticleПРОБЛЕМЫ ЯДЕРНОЙ, РАДИАЦИОННОЙ И ЭКОЛОГИЧЕСКОЙ БЕЗОПАСНОСТИTHE PROBLEMS OF NUCLEAR, RADIATION AND ECOLOGICAL SAFETYИССЛЕДОВАНИЕ АВАРИЙНЫХ СИТУАЦИЙ С ПОТЕРЕЙ ТЕПЛОНОСИТЕЛЯ НА АЭС: ВОПРОСЫ БЕЗОПАСНОСТИ ВВЭР-1000A Study of Loss of Coolant Accident (LOCA) in NPPs: a Case of Safety in VVER-1000ИдаквоА. П.IdakwoA. P.Томский государственный университетРоссияNational Research Tomsk Polytechnic University, Institute of PhysicsRussian Federation201816032026021825Copyright © Идакво А.П., 20262026Идакво А.П.Idakwo A.P.This work is licensed under a Creative Commons Attribution 4.0 License.https://glonucsec.elpub.ru/jour/article/view/472

Принятые процедуры и нормы не являются полностью адекватными, если выполняются просто механически. Уроки трех крупных ядерных аварий, в том числе, на Три-Майл-Айленд, в Чернобыле и на Фукусима Дайичи, продемонстрировали недостаточность существующих методов, стандартов и правил для предотвращения аварий. Поэтому постоянно ведется работа по предотвращению повторения таких бедствий или минимизации их последствий. Многие критерии и проекты были предложены и использованы в новых поколениях АЭС. В настоящей работе основное внимание уделяется изучению аварий с потерей теплоносителя и различным способам работы ученых и инженеров по её предотвращению и безопасному удержанию теплоносителя.

Sound procedures and good practices are not fully adequate if merely practiced mechanically. The lessons of the three major nuclear accidents including Three Mile Island, Chernobyl, and Fukushima Daiich have displayed insufficiency of existing techniques, standards and rules for their forestalling. Therefore, studies are constantly undertaken to militate against a repeat of such disaster or to limit it. Many criteria and designs have been proposed and utilized in new generations of NPP. This paper focuses on the study of loss of coolant accident (LOCA) and the various ways scientists and engineers are working to avoid and safely contain it.

АЭСВВЭР-1000ядерная безопасностьавария с потерей теплоносителяNPPVVER-1000nuclear safetycoolant accidentReferencesModarres Mohammad, Kim Seock Inn. (2010). Deterministic and Probabilistic Safety Analysis. Cacuci D.G. (ed.), Handbook of Nuclear Engineering. Vol. 1: Nuclear Engineering Fundamentals. (2185-2247). Springer Science + Business Media, LLC. New York. (in English)Modarres Mohammad, Kim Seock Inn. (2010). Deterministic and Probabilistic Safety Analysis. Cacuci D.G. (ed.), Handbook of Nuclear Engineering. Vol. 1: Nuclear Engineering Fundamentals. (2185-2247). Springer Science + Business Media, LLC. New York. (in English)Nuclear Energy Agency. (2009). Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions. State-of-the-art-Report. www.oecd.org (in English)Nuclear Energy Agency. (2009). Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions. State-of-the-art-Report. www.oecd.org (in English)United States Nuclear Regulatory Commission. Appendix A to Part 50 – General Design Criteria for Nuclear Power Plants. www.nrc.gov. visited February 27, 2018. Last updated August 29, 2017. (in English)United States Nuclear Regulatory Commission. Appendix A to Part 50 – General Design Criteria for Nuclear Power Plants. www.nrc.gov. visited February 27, 2018. Last updated August 29, 2017. (in English)Ryzhov S.B., Mokhov V.A., Nikitenko M.P., Bessalov G.G., Podshibyakin A.K., Anufriev D.A., Gado J. (ed.), Rohde U. (ed.). VVER-Type Reactors of Russian Design. Cacuci D.G. (ed.), Handbook of Nuclear Engineering. Vol. 1: Nuclear Engineering Fundamentals. (2249-2320). Springer Science + Business Media, LLC. New York. (in English)Ryzhov S.B., Mokhov V.A., Nikitenko M.P., Bessalov G.G., Podshibyakin A.K., Anufriev D.A., Gado J. (ed.), Rohde U. (ed.). VVER-Type Reactors of Russian Design. Cacuci D.G. (ed.), Handbook of Nuclear Engineering. Vol. 1: Nuclear Engineering Fundamentals. (2249-2320). Springer Science + Business Media, LLC. New York. (in English)Uffelen P.V., Konings R.J.M., Vitanza C., Tulenko J. (2010). Analysis of Reactor Fuel Rod Behaviour. Cacuci, D.G. (ed.), Handbook of Nuclear Engineering. Vol. 1: Nuclear Engineering Fundamentals. (1522-1620). Springer Science + Business Media, LLC. New York. (in English)Uffelen P.V., Konings R.J.M., Vitanza C., Tulenko J. (2010). Analysis of Reactor Fuel Rod Behaviour. Cacuci, D.G. (ed.), Handbook of Nuclear Engineering. Vol. 1: Nuclear Engineering Fundamentals. (1522-1620). Springer Science + Business Media, LLC. New York. (in English)International Atomic Energy Agency (2003). Accident Analysis for Nuclear Power Plants with Pressuried Water Reactors. Safety Report Series no 30. ISSN 1020-6450. (in English)International Atomic Energy Agency (2003). Accident Analysis for Nuclear Power Plants with Pressuried Water Reactors. Safety Report Series no 30. ISSN 1020-6450. (in English)Turinsky J. Paul. (2010). Core Isotropic Depletion and Fuel Management. Cacuci D.G. (ed.), Handbook of Nuclear Engineering. Vol. 1: Nuclear Engineering Fundamentals. (1243-1310). Springer Science + Business Media, LLC. New York. (in English)Turinsky J. Paul. (2010). Core Isotropic Depletion and Fuel Management. Cacuci D.G. (ed.), Handbook of Nuclear Engineering. Vol. 1: Nuclear Engineering Fundamentals. (1243-1310). Springer Science + Business Media, LLC. New York. (in English)

The authors declare that there are no conflicts of interest present.