ANALISIS KECELAKAAN PARAH PADA PRESSURIZED WATER REACTOR DENGAN BACKWARDS METHOD
Keywords:
Severe Accident, PWR, accident management, backwards methodAbstract
Anticipation of NPP severe accident becomes very important in nuclear technology after a severe accident at Japan's Fukushima nuclear reactor. Based on these problems then do research on the analysis of the consequences of severe accidents PWR (Pressurized Water Reactor) to learn from the Fukushima reactor accident management with a new method known as the backwards method. Backwards method is based on the results of measurements of radiation exposure received by the public, to estimate of core damage in NPP reactors. Analysis of the consequences of PWR severe accidents with bakwards method has been carried out to potential candidates site in Indonesia as Semenajung Muria, Serang Coastal, site with single weather stability such as C, D, E, and F Stability. The results of the backwards method calculation can be used to determine the severity of the accident and the verification of a particular reactor with a capacity of 1000 MWe PWR to site in Indonesia.
References
IAEA, Severe Accident Management Programmes for Nuclear Power Plants, Safety Guide, No. NS-G-2.15 ; 2009.
UNITED NATION. United Nations System-Wide Study on The Implications of the Accident at the F ukushima Daiichi Nuclear Power Plant, High - level Meeting on Nuclear Safety and Security convened by the Secretary - General, 22 September ; 2011.
Pande, M.U., Widodo, S, Setiyanto, hij Assessment of Severe Accident Consequences for Verification of Core Damaged Based on Source term release on Fukushima Accident, IAEA consultan't meeting ok Harmonization and Integration Between SAMG and EOP, Daejeon; 2011.
Francesco, D. et al, The Fukushima Event: The Outline and the Technological Background, Science and Technology of Nuclear Installations, Article ID 507921; 2012. p. 25
https://doi.org/10.1155/2012/507921
IRSN, Research and Development with Regard to Severe Accidents in Pressurised Water Reactors: Summary and outlook-Rapport CEA-2007/351; 2007. p.19-25
B. Adroguer et al, Core Loss During a Severe Accident, COLOSS Project, COLOSS Final Synthesis Report, IRSNDPAM/Dir 04/0008 SAM-COLOSS-P078; 2003.
Abdul / CIPL, Severe Accident, retrieved from File Elsevier - Petrangeli / Pageproofs /3d / H6723-Ch05.3d .2005: 60/64
Paredes, G. E., et al, Severe Accident Analysis in Nuclear Power Plants, Science and Technology of Nuclear Installations. 2012;10: 1-2
https://doi.org/10.1155/2012/430471
Van Dorsselaere, J.P, et al, The European Research on Severe Accidents in Generation-II and - III Nuclear Power Plants, Science and Technology of Nuclear Installations . 2012; 20: 65-69
https://doi.org/10.1155/2012/686945
Park S. Y., and Kwang Il AHN, Uncertainty Analysis of the Fission Product Behaviors during Severe Accidents for a Typical PWR, Progress in NUCLEAR SCIENCE and TECHNOLOGY. 2011; 1: 448-451
https://doi.org/10.15669/pnst.1.448
Hiroshi Ujita, et. al., PWR and BWR plant analyses by Severe Accident Analysis Code SAMPSON for IMPACT Project, GENES4/ANP2003,;2003. p 2-8
Soffer, L. Et al. Accident Source term for Light Water Nuclear Power Plant, Final Report. NUREG-1465. US-NUREC. Washington ; 1995.
Origen 2, Ver 2.2, CCC - 371 - RSICC, Oak Ridge National Laboratory, Tennessee; 2002.