PSA LEVEL 3 DAN IMPLEMENTASINYA PADA KAJIAN KESELAMATAN PWR
Keywords:
Level 3 PSA, accident, PWRAbstract
Reactor safety assessment of nuclear power plants using probabilistic assessment methodology is most important in addition to the deterministic assessment. The methodology of Level 3 Probabilistic Safety Assessment (PSA) is especially required to estimate severe accident or beyond design basis accidents of nuclear power plants. This method is carried out after the Fukushima accident. In this research, the postulations beyond design basis accidentsof PWR AP - 1000 would be taken, and simulated at West Bangka sample site. The series of calculations performed are: calculate the source terms of the core damaged, modeling of meteorological conditions and environmental site, exposure pathway modeling, analysis of radionuclide dispersion and transport phenomena in the environment, radionuclide deposition analysis, analysis of radiation dose, protection & mitigation analysis, and risk analysis. The assessment uses a series of subsystems on PC Cosyma software. The results prove that the safety assessment using Level 3 PSA methodology is very effective and comprehensive estimate the impact, consenquences, risks, nuclear emergency preparedness, and the reactor accident management especially for severe accidents or beyond design basis accidents of nuclear power plants. The results of the assessment can be used as a feedback to safety assessment of Level 1 PSA and Level 2 PSA.
References
IAEA-SG, Severe Accident Management Programmes for Nuclear Power Plants, IAEA - Safety Guide - NS-G-2.15, Vienna; 2009
Mitsumasa, H. Power Reactor Panel, Standards Committee, AESJ, Progress of Preparation of PSA-Related Standards by AESJ; 2005
Karanta, I., Level 3 PSA from a software architecture point of view, Research Report, VTT R-01071-13, VTT Technical Research Centre of Finland; 2013, p. 1-14
Caldwell, A. Addressing off-site consequence criteria using level 3 probabilistic, 2008
Safety assessment. MSc Thesis, KTH Royal Institute of Technology, Sweden. Report TRITA-FYS 2012:32, 2012.
Pande,M.U., Kuntjoro S., Pane J.S., Analisis Kecelakaan Parah pada Pressurized Water Reaktor dengan Backwards Method, J. Tek. Reaktor. Nukl. Vol. 15 No.1 Februari 2013, Hal. 12-26
Pande, M.U., Widodo, S, Setiyanto. The Assessment of severe accident consequences for verification of core damaged based on source term release on fukushima accident, IAEA Consultant meeting on Harmonization and Integration Between SAMG and EOP, Daejeon; 2011
Berg, H.P. Probabilistic and deterministic approaches: Taking Advantage of the Right Mix, The EUROSAFE Forum ; Paris, 2008
Röwekamp, M., et all. Probabilistic safety assesessment: Going Beyond Design Limits, IRSN, Paris, 2008, p.7-9.
Yang, J.E., Ha, J.J,Chang, S.H, PSA Classification (Introduction to Probabilistic Safety Assessment), KAERI, Daejeon, 2009.
Wooldridge, C., PCSR - Sub-chapter 15.0 - Safety requirements and PSA objectives, UKEPR-0002-150 Issue 02, Approved for AREVA, France, 2009.
IRSN, Research and Development with Regard to Severe Accidents in Pressurised Water Reactors, Summary and Outlook, Rapport IRSN-France; 2007.
BMKG. Data meteorologi Bangka. Pangkal Pinang; 2012.
BPS. Data kependudukan Provinsi Bangka; 2012.
European Commission. PC Cosyma, version 2.0. User Guide, National Radiological Protection Board, Forschungzentrum Karlsruhe GmbH; 1995
ICRP. Principles for intervention for protection of the public in radiological emergency, ICRP No. 63; 1992.
Homma, T. Level 3 PSA, accident consequence assesment methodology and its applications. Safety Analysis Laboratory; 2005.