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[en] Outlines the methodological approaches that are used to perform the sensitivity analysis of the calculation of severe accidents (SA) in the Hanhikivi NPP project, and the preliminary results of such an analysis. Severe accident scenarios for the analysis and equipment in operation were selected taking into account the requirements of Fennovoima based on the configuration of LAES-2 NPP, which is a reference design for Hanhikivi NPP
[ru]
Излагаются методологические подходы, которые используются для выполнения анализа чувствительности расчетов тяжелых аварий (ТА) в проекте АЭС “Ханхикиви”, и предварительные результаты выполнения такого анализа. Выбор сценариев ТА для анализа и состава работающего оборудования выполнен с учетом требований Fennovoima на основе конфигурации референтного к проекту “Ханхикиви”-1 проекта ЛАЭС-2Source
International Atomic Energy Agency, Vienna (International Atomic Energy Agency (IAEA)); Gosudarstvennaya Korporatsiya po Atomnoj Ehnergii Rosatom, Moscow (Russian Federation); AO Atomehnergomash, Moscow (Russian Federation); AO Kontsern Rosehnergoatom, Moscow (Russian Federation); AO Atomehnergoproekt, Moscow (Russian Federation); AO ATOMPROEKT, Sankt-Peterburg (Russian Federation); AO TVEhL, Moscow (Russian Federation); NITs Kurchatovskij Inst., Moscow (Russian Federation); AO OKB GIDROPRESS, Podol'sk (Russian Federation); vp; ISBN 978-5-94883-138-1; 
; 2015; vp; 9. International scientific and technical conference on safety assurance of NPP with WWER; 9-ya mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya Obespechenie bezopasnosti AEhS s VVEhR; Podol'sk (Russian Federation); 19-22 May 2015
; 2015; vp; 9. International scientific and technical conference on safety assurance of NPP with WWER; 9-ya mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya Obespechenie bezopasnosti AEhS s VVEhR; Podol'sk (Russian Federation); 19-22 May 2015
No abstract available
Source
Federal'noe Agentstvo po Atomnoj Ehnergii, Moscow (Russian Federation); Federal'noe Gosudarstvennoe Unitarnoe Predpriyatie Opytnoe Konstruktorskoe Byuro GIDROPRESS, Podol'sk, Moskovskaya Obl. (Russian Federation); 121 p; ISBN 978-5-94883-072-8; ; 2007; p. 36; 5. International scientific and technical conference Safety assurance for NPP with WWER; 5-ya Mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya Obespechenie bezopasnosti AEhS s VVEhR; Podol'sk, Moskovskaya Obl. (Russian Federation); 29 May - 1 Jun 2007
; 2007; p. 36; 5. International scientific and technical conference Safety assurance for NPP with WWER; 5-ya Mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya Obespechenie bezopasnosti AEhS s VVEhR; Podol'sk, Moskovskaya Obl. (Russian Federation); 29 May - 1 Jun 2007
[en] Paper studies the peculiarities of a new WWER-640 NPP equipped with passive safety systems. Paper presents a brief analysis of research efforts taken to substantiate NPP safety. Necessity to construct a large-scale integral bench ensuring complex simulation of interrelated processes in a reactor plant, containment and safety systems is shown
Journal
[en] Paper presents conceptual problems linked with safety assurance under beyond design accidents as to a WWER-640 NPP project. In compliance with the requirements of the present standard regulations and IAEA recommendations [1] the paper presents the main goals of safety and principles used to realize them in the project, the approved approach to select and to ground measures linked with control of beyond-design basis accidents and analysis of their effects. 4 refs., 1 fig
Journal
[en] Paper describes the safety concept of WWER-640 NPP determining criteria and principles of safety assurance, as well as, design approaches to implement them based on the requirements stipulated in the Russian standard technical regulations, IAEA recommendations and practice of development and approach of WWER type NPPs of earlier generations. 4 figs
Journal
[en] Paper presents the results of calculation-and-experimental studies conducted to substantiate the system of hydrogen suppression of a new generation WWER-640 NPP as to the moment of issue of preliminary report on safety, and presents the main trends of further studies up to licensing for NPP commissioning. 3 refs., 4 figs
Journal
[en] Justification of the in-vessel corium melt retention possibility is a complex task requiring for its solution of computational researches with application of special codes and experimental investigations for various physical and chemical phenomena. The results of the calculation analysis for the Russian heavy-duty code SOKRAT of the effectiveness of such a measure for the design of a reactor similar to that used in the LAES-2 project (RU WWER-1200) are considered. The obtained results made it possible to evaluate the necessity of using other technical solutions for the in-body retention of the corium in the WWER-1200 reactor. Also, the results of experimental studies carried out in support of the concept of in-vessel confinement
[ru]
Обоснование возможности удержания расплава внутри корпуса реактора является комплексной задачей, требующей выполнения расчетного и экспериментального обоснования различных физических и химических явлений. Рассмотрены результаты расчетного анализа по российскому тяжелоаварийному коду СОКРАТ эффективности такой меры для конструкции реактора, аналогичной использованной в проекте ЛАЭС-2 (РУ ВВЭР-1200). Полученные результаты позволили оценить необходимость использования других технических решений для внутрикорпусного удержания кориума в РУ ВВЭР-1200. Также приводятся результаты экспериментальных исследований, выполненных в поддержку рассматриваемой концепции внутрикорпусного удержанияSource
International Atomic Energy Agency, Vienna (International Atomic Energy Agency (IAEA)); Gosudarstvennaya Korporatsiya po Atomnoj Ehnergii Rosatom, Moscow (Russian Federation); AO Atomehnergomash, Moscow (Russian Federation); AO Kontsern Rosehnergoatom, Moscow (Russian Federation); AO Atomehnergoproekt, Moscow (Russian Federation); AO ATOMPROEKT, Sankt-Peterburg (Russian Federation); AO TVEhL, Moscow (Russian Federation); NITs Kurchatovskij Inst., Moscow (Russian Federation); AO OKB GIDROPRESS, Podol'sk (Russian Federation); vp; ISBN 978-5-94883-138-1; ; 2015; vp; 9. International scientific and technical conference on safety assurance of NPP with WWER; 9-ya mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya Obespechenie bezopasnosti AEhS s VVEhR; Podol'sk (Russian Federation); 19-22 May 2015; 4 figs., 1 tab.
; 2015; vp; 9. International scientific and technical conference on safety assurance of NPP with WWER; 9-ya mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya Obespechenie bezopasnosti AEhS s VVEhR; Podol'sk (Russian Federation); 19-22 May 2015; 4 figs., 1 tab.
No abstract available
Source
Trufanov, A.A.; Sorokin, A.P. (eds.); Predpriyatie Goskorporatsii Rosatom AO Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii - Fiziko-Ehnergeticheskij Inst. imeni A.I. Lejpunskogo, Obninsk (Russian Federation); 202 p; ISBN 978-5-906512-82-6; ; 2016; p. 137-138; Thermal physics 2016: Thermal physics of new generation reactors; Teplofizika reaktorov novogo pokoleniya (Teplofizika-2016); Obninsk (Russian Federation); 12-14 Oct 2016; 1 fig.
; 2016; p. 137-138; Thermal physics 2016: Thermal physics of new generation reactors; Teplofizika reaktorov novogo pokoleniya (Teplofizika-2016); Obninsk (Russian Federation); 12-14 Oct 2016; 1 fig.
[en] The paper presents the developed principles of mathematical and physical simulation of aerohydrodynamic, thermophysical, physical and chemical processes under the containment of nuclear power plants in case of LACAs. The characteristics of the system of KUPOL-PhEI numeric codes and physical models for 1, 2, 5, 8, 100 and 3200 m3 volumes are given. Preliminary results of partial verification of codes and specific results of the experiments and numeric analysis are presented. 19 refs.; 8 figs.; 1 tab
Journal
No abstract available
Source
GK Rosatom, Moscow (Russian Federation); Rossijskaya Akademiya Nauk, Moscow (Russian Federation); GNTs RF - FEhI, Obninsk (Russian Federation); NOU DPO TsIPK Rosatoma, Obninsk (Russian Federation); IBRAEh RAN, Moscow (Russian Federation); 348 p; ISBN 978-5-85855-038-8; ; 2015; p. 47-48; 10. anniversary Russian scientific conference on radiation protection and radiation safety in nuclear technologies; 10-ya yubilejnaya Rossijskaya nauchnaya konferentsiya Radiatsionnaya zashchita i radiatsionnaya bezopasnost' v yadernykh tekhnologiyakh; Moscow (Russian Federation); 22-25 Sep 2015; 2 refs.
; 2015; p. 47-48; 10. anniversary Russian scientific conference on radiation protection and radiation safety in nuclear technologies; 10-ya yubilejnaya Rossijskaya nauchnaya konferentsiya Radiatsionnaya zashchita i radiatsionnaya bezopasnost' v yadernykh tekhnologiyakh; Moscow (Russian Federation); 22-25 Sep 2015; 2 refs.
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