PENGARUH DAYA DAN DURASI OPERASI REAKTOR TERHADAP KONSENTRASI 3H DAN 14C DI AIR SISTEM PENDINGIN PRIMER REAKTOR RSG-GAS
Keywords:
primary water reactor, 3H, 14C, RSG-GAS reactorAbstract
The influence of reactor power and operation duration on concentration of 3H and 14C in primary coolant water system RSG-GAS reactor has been studied. The existence of nuclides 3H and 14C in primary coolant system RSG-GAS reactor is a result of fission product and activation. These nuclides have potential internal and external radiation hazard, due to long half life i.e. 12,26 years and 5568 years for 3H and 14C respectively, so that will have significant radiological impact. Analysis and water sample measurement of the primary coolant system has been done by using LSC (Liquid Scintillation Counter). The objective of this research is to study the influence of reactor power and its operation duration to 3H and 14C concentration in coolant system, the correlation of these nuclide concentration with reactor system related to the component ageing, and estimation of receiving RSG-GAS reactor worker radiation for safety in working area and personnel safety. The results showed that 3H and 14C concentration in RSG-GAS reactor are proportional to the reactor power and its operation time duration. The fast increasing of 3H and 14C concentration in RSG-GAS reactor primary coolant system after the first five years operation might be caused by high intensity of reactor operation, and the accumulation of long half life nuclides. The results of this research can be used to study the reactor operation safety, personnel and working area safety, and also to study the reactor ageing process.
References
Argonne National Laboratory, EVS. Tritium (Hydrogen-3), Human Health Fact Sheet; August 2005
Checev, V. P and Egorov, A. G. Search for an optimum approach to the evaluation of data of varying consistency: half-live evaluations for 3H, 35S, 55Fe, 99Mo, and 111In. Appl. Radiat. Isot. 2000; 52: 601-608.
https://doi.org/10.1016/S0969-8043(99)00217-1
BATAN, Multipurpose Reactor GA Siwabessy. Safety Analisis Report Rev.9 2005
Oldenberg O., Rosmussen. Modern Physics for Engineers. New York: Mc. Graw-Hill; 1986.
Unterweger, M. P. and Lucas, L. L. Calibration of the national institute of standards and technology tritiated-water standards. Appl. Radiation Isotop 2000; 52: 527-531.
https://doi.org/10.1016/S0969-8043(99)00205-5
Verrezen, V. and Hurtgen, C. A multiple window deconvolution technique for measuring low-energy beta activity in samples contaminated with high-energy beta impurities using liquid scintillation spectrometry. Appl. Rad. and Isotopes 2000; 53: 289-296.
https://doi.org/10.1016/S0969-8043(00)00143-3
PRSG-BATAN. Laporan Operasi RSG-GAS, Serpong; 2009
Pande, M.U. Konsentrasi h3 dan c14 pada air sistem pendingin primer rsg-gas selama 5 tahun pertama operasi reaktor. Proseding Pertemuan dan Presentasi Ilmiah Penelitian dasar Ilmu Pengetahuan dan Teknologi Nuklir. Yogyakarta; 1993
National research council. Board on radiation effects research, health risks from exposure to low levels of ionizing radiation: BEIR VII Phase 2. The National Academies Press. Washington DC; 2006.
Pande, M.U., Bunawas, Budi R. Pengukuran konsentrasi tritium di udara reaktor Serbaguna G.A. Siwabessy. Proseding Presentasi Ilmiah Keselamatan Radiasi dan Lingkungan. Jakarta; 1994.
BAPETEN. Ketentuan Keselamatan Kerja. S.K. Ka.BAPETEN no.1. Jakarta; 2003
Cardis, E,., et al. Risk of cancer after low doses of ionizing radiation: retrospective cohort study in 15 countries. BMJ. 2005 Jul 9; 331
Harrison J.D., Khursheed, A., Lambert, B.E. Uncertainties in dose coefficients for intakes of tritiated water and organically-bound forms of tritium by Members of the Public. Radiat. Prot Dosim 2002; Vol 98 No. 3 pp 299-311.
