Nuclear power plant safety assessment and accident management : Practice in Sweden and computerized decision support systems

• Autorzy: Frid W.
• Języki publikacji: EN

Abstrakty

EN

The methods of nuclear power plant safety assessment and accident management used in Sweden and selected computerized decision support systems are briefly described. The defense-in-depth strategy, which comprises three elements, namely prevention, protection and mitigation, is essential for keeping the fission product barriers intact. The safety assessment program, which focuses on prevention of incidents and accidents, has three main components: periodic safety reviews, probabilistic safety analysis and analysis of postulated disturbances and accident progression sequences. Even if prevention of accidents is the first priority, it is recognized that accidents involving severe core damage, including core melt, may nevertheless occur. Therefore, measures are required to achieve reasonable capability to manage such accidents. Emergency Operating Procedures and Severe Accident Management Guidelines are the vital components of the Accident Management System. Computerized decision support systems, to be used during normal, disturbed and accident states of a plant are expected to play increasingly important role in safety assessment and accident management, including support in rapid evaluation of possible radioactive releases in the event of a severe accident.

Słowa kluczowe

EN

nuclear power; Accident Management System

PL

energia jądrowa

• Wydawca: Instytut Podstawowych Problemów Techniki PAN
• Czasopismo: Computer Assisted Mechanics and Engineering Sciences
• Rocznik: 2002
• Tom: Vol. 9, No. 1
• Strony: 41--54
• Opis fizyczny: Bibliogr. 18 poz., rys.

Twórcy

autor

Frid W.

• Royal Institute of Technology, Department of Nuclear Engineering, Brinellvägen 60, SE-100 44 Stockholm, Sweden

Bibliografia

• [1] F. Adorján, A. Horneas, Cs. Horvath, J.E. Hulsund, Gy. Kapocs, S. Lipcsei, Cs. Major, J. Vegh. The EOP visualization module integrated into the PLASMA on-line nuclear power plant safety monitoring and assessment system. International Topical Meeting on Nuclear Plant Instrumentation, Controls, and Human-Machine Interface Technologies (NPIC&HMIT 2000), Washongton, DC, November, 2000.
• [2] T. Engquist, T. Lehto, B. Jansson. Principles and development strategies for procedures with focus on abnoral situations. IAEA Specialist Meeting on Operating Procedures for Nuclear Power Plants and their Presenatation, Wien, March 31 April 2, 1992.
• [3] H. Esmaili, S. Orandi, R. Vijaykumar, M. Khatib-Rahbar, O. Zuchuat, U. Schmocker. ADAM: An accident diagnostics, analysis and management system. In: G. Guedes Soares, ed., Advances in Safety & Reliability, p. 257, 1997.
• [4] P. Fantoni, Y. Iguchi, G. Meyer, A. Sörenssen, C. Van Dycke CAMS Achievments in 1996. NKS/RAK-2(97)TRB3, OECD Halden Reactor Project, 1997.
• [5] P. Fantoni, M. Hoffmann, B. H. Nystad, M. V. Oliviera. Integration of sensor validation in alarm structuring and suppression. International Topical Meeting on Nuclear Plant Instrumentation, Controls, and Human-Machine Interface Technologies (NPIC&HMIT 2000), Washongton, DC, November, 2000.
• [6] W. Frid, ed. Severe Accident and Management in Nordic Countries: A Status Report. NKS/SOS-2.3 Project. SKI Rapport 00:46, 2000.
• [7] L. Högberg. The Swedish program on severe accident management release mitigation. Int. Symp. On Severe Accidents in Nuclear Power Plants, Sorrento Italy, 1988
• [8] J. Holmberg, K. Laakso, E. Lechtinen, G. Johanson. Safety Evaluation by Living Probabilistic Safety Indicators. Final Report of the NKS Project SIK-1, Tema Nord 1994:614, 1994.
• [9] G. Löwenhielm et al.. Verification of accident management strategies at the Forsmark Plant. OECD/CSNI Specialist Meeting on Severe Accident Management Development, Rome, Sept. 1991.
• [10] G. Löwenhielm, B. Jansson, V. Gustavsson. New ideas about procedures and handbooks for severe accident management at the Forsmark eeting on Severe Accident Management Strategies at the Forsmark Nuclear Power Plants. The Fifth International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-5), China, 1997
• [11] F. Övre, C. Holmström, S. Nilsen, P. van Gemst. Safety Assessment and Post Trip Guidance – The SAS II Project for the Forsmark NPP: A Final Report. OECD Halden Reactor Project, HPR-342, February 1993.
• [12] B Pershagen. Light Water Reactor Safety. Pergamon Press, 1989.
• [13] Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. USAEC Report WASH-1400, U.S. Nuclear Regulatory Commission, October 1975.
• [14] C. Rojas-Palma et al. On and off-site source term estimation during nuclear emergencies. 7th Topical Meeting on Emergency Preparedness and Response. California, USA, September 1999.
• [15] A. Santinelli et al. Operator Assisting Systems for Accident Management, State of the Art Report. Europen Commission, EUR 16925 EN, 1996. |
• [16] Severe Accident Management: Prevention and Mitigation. OECD, Nuclear Energy Agency, Paris 1992.
• [17] E. Söderman, ed. Severe Accident Analysis in Sweden — Methods and Results. RAMA III Final report, RAMA III 89-02, Studsvik Library, Sweden, December 1989.
• [18] "The T-Bok”, Reliability Data of Components in Nordic Reactor Power Plants, Fourth Edition. Jointly published ; by the Nordic utilities and SKI, 1994.