RADIONUKLIDA CESIUM SEBAGAI INDIKATOR PENENTUAN BURNUP BAHAN BAKAR U3Si2/Al SECARA MERUSAK
DOI:
https://doi.org/10.17146/urania.2022.28.3.6711Keywords:
Destructive method, separation, cesium, burnupAbstract
Determination of burn-up using a destructive method was carried out by separation of 137Cs in the irradiated U3Si2/Al fuel element plate (FEP) with a density of 4.8 gU/cm3. Determination of burn-up by the destructive method aims to study the suitability of the burn-up obtained by the non-destructive method or using the Origen Code software. FEP U3Si2/Al with CBBJ code 251 was cut in duplo at the top, middle and bottom with a weight of Top-1= 0.049 gFEP and Top-2=0.058 gFEP, Middle-1= 0.055 gFEP and Middle-2= 0.024 gFEP, and Bottom-1= 0.056 gFEP and Bottom-2=0.075gFEP. FEP samples were dissolved in acid to obtain a fuel solution containing fission products of 134Cs, 137Cs, 235U and other isotopes. The fuel solution was pipetted 1 mL and then transferred from the hot cell to R.135 to separate the 137Cs from 235U by a cation exchange method using zeolite from Lampung. The fuel solution was pipetted 100 μL and put into the vial in duplicate, then 1000 mg Lampung zeolite was added to the cation exchange process. The separation results were 137Cs in solid phase, while uranium and other isotopes in liquid phase. The amount of activity (Bq) of the 137Cs isotope was measured with a Spectrometer- and then used for burn-up calculation. The results of the calculation of the burn-up were 26.9714%; 55,1431%; and 37.8855% for the top, middle and bottom pieces, respectively, with an average burn-up by 40%. These values are not much different from the burn-up obtained by the non-destructive method using gamma scanning, i.e., 24.4%; 52.7% ; and 37.6% for top, middle and bottom positions with an average of 38.23% and a burn-up calculated using the Origen code, which is 40%.
References
. Supardjo, T. Surbakti, E. P. Hastuti, A. Hamzah, A. B. Ginting, "Teknik pembuatan dan pengujian bahan bakar dispersi U3Si2/Al densitas uranium tinggi," Buku Batan Press, hal 64-70, 2019.
. P. H. Liem, T. M. Sembiring, "Design of transition cores of RSG GAS (MPR-30) with higher loading silicide fuel," Nuclear Engineering and Design, vol. 240, pp. 1433-1442, 2010.
https://doi.org/10.1016/j.nucengdes.2010.01.028
. S. K. Jung, S. J. Young, D. P. Soon, K. H. Yeong, S. Kyuseok, "Analysis of high burnup pressurized water reactor fuel using uranium, plutonium, neodymium, and cesium isotop correlations with burn-up," Nuclear Engineering Technology, vol. 471, pp. 924-933, 2015.
https://doi.org/10.1016/j.net.2015.08.002
. P. H. Liem, S. Amini, A. G. Hutagaol, and T. M. Sembiring, "Nondestructive burnup verification by gamma-ray spectroscopy of LEU silicide fuel plates irradiated in the RSG GAS multipurpose reactor," Annals Nuclear Energy, vol. 56, pp. 57-65, 2013.
https://doi.org/10.1016/j.anucene.2013.01.013
. Monographic BIPM-5-Table of Radionuclides, Comments on Evaluations, 2010, volume 5, Published by the LNHB or in the web pages: http://www.nucleide.org/NucData.htm.
. R. Artika, R. Sigit, H. F. Rahmatullah, A. B. Ginting, Supardjo, "Uji tak merusak pelat elemen bakar U3Si2/Al densitas uranium 4,8 gU/cm3 menggunakan radiografi sinar-x digital," Jurnal Ilmiah Daur Bahan Bakar Nuklir Urania, vol. 26, no. 1, hal. 49-56, 2020.
https://doi.org/10.17146/urania.2020.26.1.5822
. Y. J. Kim, B. O. Yoo, H. M. Kim, S. B. Ahn, "Development of X-ray system for irradiated fuel in hot cell," Hotlab Conference Proceeding 2016, Karsruhe, Germany.
. Y. Nampira dan S. Ismarwanti, "Uji tidak merusak bahan bakar U3Si2-Al tingkat muat uranium 4,8 g/cm3 pasca iradiasi fraksi bakar 20% dan 40%," Jurnal Teknologi Bahan Nuklir, vol. 10, no. 2, hal. 53-63, 2014.
. A. B. Ginting, Supardjo, Yanlinastuti, S.Indaryati, Boybul, "Perhitungan burn up PEB U3Si2/Al densitas 4,8 gU/cm3 pasca iradiasi potongan bagian middle," Jurnal Ilmiah Daur Bahan Bakar Nuklir Urania, vol. 25, no. 2, hal. 91-106, 2020.
https://doi.org/10.17146/urania.2020.26.2.5864
. H. U. Zwicky, J. Low, M. Granfors, C. Alejano, J. M. Conde, C. Casado, J. Sabater, M. Llore, M. Quecedo, J. A. Gago, "Nuclide analysis in high burn-up fuel samples irradiated in Vandellós 2," Journal of Nuclear Materials, vol. 402, pp. 60-73, 2010.
https://doi.org/10.1016/j.jnucmat.2010.04.023
. A. B. Ginting and P. H. Liem, "Absolute burn-up measurement of LEU silicide fuel plate irradiated in the RSG GAS multipurpose reactor by destructive radiochemical technique," Annals Nuclear Energy, vol. 85, pp. 613-620, 2015.
https://doi.org/10.1016/j.anucene.2015.06.016
. A. B. Ginting, S. Amini, Noviarty, Yanlinastuti, A. Nugroho, Boybul, "Natural zeolite as a replacement for resin in the cation exchange process of cesium on post-irradiated nuclear fuel," Nukleonika, vol. 66, no.1, pp.11−19, 2021.
https://doi.org/10.2478/nuka-2021-0002
. A. Sukur, A. Azira and H. A. Husni, "Determination of cation exchange capacity of natural zeolite," Malaysian Journal of Soil Science, vol. 21, pp.102-112, 2017.
. B. Wiyantoko and N. Rahmah, "Measurement of cation exchange capacity (CEC) on natural zeolite by percolation methode," AIP Conference Proceedings 1911, 020012, 2017. Published On line 05 December 2017.
https://doi.org/10.1063/1.5016014
. A. G. Volkov, S. Paula, D. W. Deamer, "Two mechanisms of permeation of small neutral molecules and hydrated ions across phospholipid bilayers," Bioelectrochem. Bioenergetics, vol. 42, pp. 153-160, 1997.
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