Global Nuclear Safety
National Research Nuclear University "MEPhI"
online version: ISSN 2499-9733
print version: ISSN 2305-414Х
2014-1(10)
Nuclear, radiation and environmental safety
| Article Name | Calculation Modeling and Assessment of Containment Heat Removal Passive System Effectiveness in Case of Break Steam Pipe of the Steam Generator on NPP with WWER-1000 |
|---|---|
| Authors | Kh.M. Naffaa*, D.V. Shevielov **, A.S. Balashevskyi** |
| Address | * Sevastopol National University of Nuclear Energy and Industry, 7 Kurchatova St., Sevastopol, Ukraine (since 21.03.2014 – Russian Federation) 99015 ** Sevastopol Branch of Scientific and Technical Support SE STC of SE NNEGC “Energoatom”, 7 Kurchatova St., Sevastopol, Ukraine (since 21.03.2014 – Russian Federation) 99015 |
| Abstract | The article considers the results of the passive system modeling of heat removal for beyond design basis accident in the break steam pipe case of the steam generator inside the containment with the loss of station power. It is shown the passive system effectiveness of heat removal from containment for analyzing of beyond design basis accident at NPP with WWER-1000. The calculations were performed using MELCOR 1.8.5 code. |
| Keywords | passive system of heat removal (PSHR), containment, steam generator (SG), nuclear power plant (NPP), emergency feedwater (EFW), reactor facility (RF), water-water energetic reactor (WWER), beyond design basis accident (BDBA), two-phase thermosyphon (TPT) |
| Language | Russian |
| References | [1] Naffaa H.M., Sviridenko I.I., Shevelev D.V. Passivnye sistemy ohlazhdenija zashhitnyh obolochek reaktornyh ustanovok [Passive cooling systems of reactor installation protective covers]. Zb. nauk. pr. SNUJaEtaP [Collection of scientific works of Sevastopol National University of Nuclear Energy and Industry]. Sevastopol: SNUJaJeiP. [Sevastopol, Sevastopol National University of Nuclear Energy and Industry], 2012, №2(42), pp. 46–55. (in Russian) [2] Design of Reactor Containment Systems for Nuclear Power Plants. IAEA safety standards series. No. NS-G-1.10, 2004. 127 р. (in English) [3] Lee S.-W. Assessment of Passive Containment Cooling Concepts for Advanced Pressurized Water Reactors. Ann. Nucl. Energy, 1997, Vol. 24, No. 6. pp. 467–475. (in English) [4] Passive Safety system and Natural Circulation in Water Cooled Nuclear Power Plants. IAEA-TECDOC-1624. Vienna: IAEA, 2009, 159 р. (in English) [5] Naffaa, H.M. Gerliga V.A., Shevelev D.V., Balashevskij A.S. Ocenka jeffektivnosti sistemy passivnogo otvoda tepla ot zashhitnoj obolochki RU s VVJeR v uslovijah dlitel'nogo obestochivanija [Assessment of system effectiveness of passive heat removal from a protective cover reactor facility with WWER in the long de-energization conditions]. Jadernaja i radiacionnaja bezopasnost [Nuclear and radiation safety]. Kiev, №2(58). p. 27–31. (in Russian) [6] Naffaa H.M., Shevelev D.V., Balashevskij A.S. Raschetnoe modelirovanie raboty i ocenka jeffektivnosti sistemy passivnogo otvoda teploty ot germoob’ema (SPOT) pri tjazhelyh avarijah na AJeS s VVJeR-1000 [Settlement work modeling and system effectiveness assessment of passive bend of warmth from a hermetic volume (SPOT) at severe accidents at the NPP with WWER-1000]. Globalnaja jadernaja bezopasnost [Global Nuclear Safety]. 2013, 3(8), ISSN 2304-414X, pp. 9–18. (in Russian) [7] Zaporozhskaja AJeS. Jenergoblok № 5. Baza dannyh po JaPPU dlja celej AZPA. ER37-2006.310.OD (2) [Zaporozhye NPP. Power unit № 5. NSSS database for the beyond design basis acciden purposes. ER37-2006.310.OD (2)]. Kiev, 2008. (in Russian) |
| Papers | 10 - 15 |
| URL Article | URL Article |
| Open Article |