Global Nuclear Safety
National Research Nuclear University "MEPhI"
online version: ISSN 2499-9733
print version: ISSN 2305-414Х
2018-2(27)
Nuclear, radiation and environmental safety
| Article Name | A Study of Loss of Coolant Accident (LOCA) in NPPs: a Case of Safety in VVER-1000 |
|---|---|
| Authors | Idakwo Ako Paul |
| Address | National Research Tomsk Polytechnic University, Institute of Physics |
| Abstract | 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. |
| Keywords | NPP, VVER-1000, nuclear safety, coolant accident |
| Language | English |
| References | [1] 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) [2] Nuclear Energy Agency. (2009). Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions. State-of-the-art-Report. www.oecd.org (in English) [3] 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) [4] 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) [5] 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) [6] 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) [7] 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) |
| Papers | 18 - 25 |
| URL Article | URL Article |
| Open Article |