KARAKTERISASI RADIONUKLIDA PADA TIAP SUB-SISTEM KESELAMATAN REAKTOR DAYA BERBAHAN BAKAR MOX
Keywords:
nuclide characteristic, power reactor, fuel, MOXAbstract
Substitute UO2 fuel that low enrichment of uranium is that MOX fuel has a higher enrichment. MOX fuel has a content of plutonium and actinide nuclides a higher than UO2 fuel, which will produce different characteristics of radionuclides for each sub-system of power reactors. Analyzis of radionuclide for each safety sub-system at MOX power reactor aims to determine the characteristics of radionuclides, especially plutonium and actinides consequences. Analyzis has done by calculating and observing the radionuclide for each safety sub-system in normal operation and accident (small LOCA, large LOCA, and severe accident) on PWR-1000 reactors. It can concluded that the use of MOX fuel can add to the radiological consequences to the environment and public, mainly because a larger inventory of radionuclides, including transuranic radionuclides and the actinide group, among others: Pu-239, Am-241, Cm-242, Pu-240, Pu -241 and Pu-242.
References
Lyman E. S. Public Health Risks of Substituting Mixed-Oxide for Uranium Fuel in Pressurized Water Reactors, Science & Global Security. 2001;9 : p 33-79
https://doi.org/10.1080/08929880108426486
BATAN, Multipurpose Reactor GA Siwabessy, Safety Analysis Report, Rev. 9; 2001: 12-5.
Pershagen, B. Light Water Reactor Safety, Pergamon Press, New York, 1988
https://doi.org/10.1016/B978-0-08-035915-1.50020-5
European Commission, Determination of the In-Sungkup Source term for a Large-Break Loss of Coolant Accident, EUR 19841 EN; 2001: p. 11-7
IRSN, Research and Development with Regard to Severe Accidents in Pressurised Water Reactors, Summary and Outlook, Rapport IRSN-France; 2007
Glatz J.P, Giménez J. and Bottomley D, Leaching of High Burn-up UO2 and MOX Fuel Rods with Pre-Set Cladding Defects, WM99 Conference , European commission, Directorate General JRC, Institute for Transuranium Elements (ITU) P.O. Box 2340, D76125 Karlsruhe, Germany 1999
Crawford D, LWR Fuel Performance (with emphasis on BWR fuel), Fuel Performance & Design, Global Nuclear Fuel, Wilmington NC; 2009: p. 1-12
Lovasic Z. and Einziger R. International Atomic Energy Agency (IAEA) Activity on Technical Influence of High Burnup UOX and MOX Water Reactor Fuel on Spent Fuel Management - 9065, WM2009 Conference. Phoenix, AZ; 2009: p. 1-6
IAEA, Generic Models for use in Assessing the Impact of Discharges of Radioactive Substances to The Environment, Safety series No.19, STI/PUB/1103, Vienna; 2001
EUR, Generic Nuclear Island Requirements-Safety Requirements, Vol.2, Chap. 1, Rev. C, European Utility Requirements for LWR Nuclear Power Plants , 2001
ORIGEN2, Ver 2.2, CCC-371- RSICC, Oak Ridge National Laboratory, Tennessee; 2002