Role of passive safety systems in prevention and mitigation of severe accidents at nuclear power plants
DOI:
https://doi.org/10.15276/opu.2.66.2022.03Keywords:
NPP, VVER, severe accident, passive safety system, passive heat removal system, reliabilityAbstract
Fukushima Daiichi accidents led to the worldwide update of the NPP safety requirements. Particular attention was paid to severe accidents both during the design of new NPP units and during the safety reassessment of existing ones. Performed safety reassessment of operating units was focused on development and implementation of technical means and strategies directed to prevention and/or mitigation of severe accidents. Technical solutions that are used in modern designs of reactor facilities involve several options for providing of heat removal from the core and containment. Such options include heat removal systems from the reactor core and from the containment of reactor facility. Most of such systems are based on passive principals of operation and do not require or require a minimum action of operating personnel. At the same time, reactor facilities that are operated in Ukraine are based on old VVER designs, which do not include passive safety systems for long-term heat removal (especially for the case of total station blackout, which was in the focus during safety reassessments, so-called “stress tests”). Thus, the necessity of such systems at Ukrainian NPPs with VVER-1000 and VVER-440 was discussed together with analysis of existing types of passive systems and their prevalence. Based on the results of performed analysis the feasibility of implementation at Ukrainian NPPs of a passive heat removal system from the core for VVER-1000 and from the confinement for the VVER-440 was identified. The possibility of implementation of such systems at Ukrainian NPPs requires a separate analysis. In addition, a general information on current state of passive systems reliability assessment was described. It should be noted that despite the reliability of passive safety systems is one of the important issues it is still poorly studied and require additional analyses.
Downloads
References
SSR-2/1 (Rev. 1). Safety of nuclear power plants: design. IAEA safety standards series. International Atomic Energy Agency. Vienna, 2016. 71 p.
Council Directive 2014/87/EURATOM of 8 July 2014 amending Directive 2009/71/Euratom establishing a Community framework for the nuclear safety of nuclear installations.
WENRA Safety Reference Levels for Existing Reactors. Report. Update in Relation To Lessons Learned From TEPCO Fukushima Daiichi Accident. 24th September 2014. 13 p.
Diverse and Flexible Coping Strategies (FLEX) Implementation Guide. Nuclear Energy Institute. NEI 12-06, Rev. 1, 2012. 104 p. URL: http://pbadupws.nrc.gov/ docs / ML1214/ML12143A232.pdf.
International Atomic Energy Agency, Status of advanced light water reactor designs, p. 715–732, IAEA, IAEA-TECDOC-1391, Vienna 2004.
Takano K., et al., Integrated Modular Water Reactor (IMR), Development for Practical Application in the Near Future, Proc. of 14th Pacific Basin Nuclear Conference (PBNC 14th), Honolulu, USA 2004.
International Atomic Energy Agency, Fundamental Safety Principles, IAEA. Safety Standards, Safety Fundamentals, No. SF-1, IAEA, Vienna 2006.
AEA Safety Standards for protecting people and the environment, Safety of Nuclear Power Plants: Design. Specific Safety Requirements. No. SSR-2/1 (Rev. 1), Vienna 2016.
IAEA-TECDOC-626. Safety related terms for advanced nuclear plants. IAEA, Vienna, 1991.
IAEA-TECDOC-1624. Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants, Vienna, 2009.
НП 306.2.141-2008. Загальні положення безпеки атомних станцій.
НП 306.2.204-2016. Вимоги до систем аварійного охолодження ядерного палива та відведення тепла до кінцевого поглинача.
Наффа Х.М., Дубковский В.А. Классификация систем пассивного отвода остаточных тепловыделений от защитных оболочек ядерных реакторов. Праці Одеського політехнічного університету, 2014. Вип. 1(43). C. 104 – 111.
Pierro F., Araneo D., Galassi G., D’Auria F.. Application of REPAS Methodology to Assess the Reliability of Passive Safety Systems. Science and Technology of Nuclear Installations. 2009. Article ID 768947. 18 p. DOI: 10.1155/2009/768947.
Bucknor M., Grabaskasa D., Brunetta A. The Development of a Demonstration Passive System Reliability Assessment. 12th International Conference on Probabilistic Safety Assessment and Management PSAM 12, June 22-27, 2014, Honolulu, HI, USA.
Passive system reliability analysis using the APSRA methodology / A.K. Nayaka, M.R. Gartia, A. Antony, G. Vinod, R.K. Sinha. Nuclear Engineering and Design. 2008. 238. P. 1430–1440.
Vyshemirskij M.P., Zhabin O.I., Ostapchuk S.A. Analysis of steam generator feeding with a mobile pump unit during a total NPP blackout with a VVER-1000/V-320 reactor facility. Nuclear and Radiation Safety. 2016. 4 (72). P. 25–31.