Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor
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Sriyono Sriyono
, Deden Saprudin
, Mohamad Rafi
, Geni R. Sunaryo
, Nugraha Luhur
Abstract
The liquid radioactive waste generated by the G.A. Siwabessy reactor (RSG-GAS) is categorized into low-activity liquid radwaste (LALR) and medium-activity liquid radwaste (MALR). The radionuclide content of both LALR and MALR can use as an indicator of the structural integrity of the reactor’s systems, structures, and components (SSC). To evaluate the degradation of the reactor SSC, the radionuclide species were identified, and their activities were measured using gamma spectroscopy. Based on the identified radionuclides, the process of their formation can be traced. The radionuclides identified in LALR were 24Na, 51Cr, 59Fe, 60Co, 65Zn, and 124Sb, while the radionuclides in MALR were 24Na, 51Cr, 58Co, 59Fe, 60Co, 65Ni, 65Zn, 89Kr, 90Kr, 109Cd, 131I, 132I, 140Ba, 137Cs, 146Ce, and several others. The radionuclides found can be classified into corrosion product activation (60Co, 65Zn, 51Cr, 59Fe, 24Na, 65Ni), topaz impurities activation (51Cr, 59Fe, 60Co, 65Zn), fission product (90Kr, 140Ba, 131I, 137Cs, etc.), and demineralized water impurities activation (51Cr, 59Fe, 65Zn, 60Co, etc.). After comparing the activity value of each radionuclide with the limit value in the safety analysis report document, we can conclude that the activity of each one is below the required level. It can infer that the structural integrity of reactor SSC is still well maintain. During routine monitoring, the radionuclide content in the primary coolant fluctuates depending on the reactor load. The concentration of radionuclides detected varies when a large or small number of research samples are loaded onto the core. Nevertheless, their activities remain within the required safety limits.
Funding source: BRIN Indonesia
Award Identifier / Grant number: B-265/V/TN/4/2022
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Research funding: This research is supported by the National Research and Innovation Agency of Indonesia (BRIN) through the degree by research (DBR) scholarship scheme and Government of Republic of Indonesia finance budget under Rumah Program HITN-2023.
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Author contributions: All authors contributed equally in this research.
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Conflict of interest statement: There is no conflict of interest.
References
AZO (2015). Grade 304 stainless steel: properties, fabrication and applications. In: AZO materials handbook. AZO Materials, Manchester, UK, pp. 1–12. https://www.azom.com/article.aspx?ArticleID=2867.Search in Google Scholar
Chmielewski, A.G. and Szołucha, M.M. (2016). Radiation chemistry for modern nuclear energy development. Radiat. Phys. Chem. 124: 235–240, https://doi.org/10.1016/j.radphyschem.2016.01.002.Search in Google Scholar
Febrianto, F., Saragi, E., Hafid, A., Sriyono, S., and Lestari, D.E. (2016). Analysis of AlMg3 material corrosion as RSG-GAS beam tube. In: Proceeding of National seminar on nuclear energy technology. PKSEN-BATAN, Jakarta, pp. 321–326. https://inis.iaea.org/collection/NCLCollectionStore/_Public/52/095/52095762.pdf.Search in Google Scholar
Febrianto, F., Sriyono, S., Hastuti, E.P., and Sunaryo, G.R. (2019). Study on pitting corrosion of AlMg2 in solution containing chloride. Journal of Physics: Conference Series 1198: 1–7, https://doi.org/10.1088/1742-6596/1198/2/022061.Search in Google Scholar
Ginting, A. and Liem, P.H. (2015). Absolute burnup measurement of LEU silicide fuel plate irradiated in the RSG GAS multipurpose reactor by destructive radiochemical technique. Ann. Nucl. Energy 85: 613–620, https://doi.org/10.1016/j.anucene.2015.06.016.Search in Google Scholar
Hartoyo, U., Rohidi, R., Setiawanto, A., and Subiharto, S. (2014). Liquid radwaste disposal control from KPK01 of RSG-GAS for environmental safety. In: Proceeding of national seminar on reactor application and technology. PRSG-BATAN, Jakarta, pp. 163–168. https://karya.brin.go.id/id/eprint/1595/.Search in Google Scholar
Hummel, D.W., Chouhan, S., Lebel, L., and Morreale, A. (2020). Radiation dose consequences of postulated limiting accidents in small modular reactors to inform emergency planning zone size requirements. Ann. Nucl. Energy 137: 107062, https://doi.org/10.1016/j.anucene.2019.107062.Search in Google Scholar
IAEA (2014). IAEA safety standards: the classification of radioactive wastes. General Safety Guide, International Atomic Energy Agency, No. GSG-1.Search in Google Scholar
IAEA (2018). Safety standards for protecting people and the environment general safety guide No. GSG-7 occupational radiation protection, general safety guide international atomic energy agency, Available at: <http://www-ns.iaea.org/standards/>.Search in Google Scholar
IAEA (2022). Handling and Processing of radioactive Waste from nuclear applications, Technical Report Series 402.Search in Google Scholar
Kissane, M. and Housiadas, C. (2012). Fission product release and transport. In: Nuclear safety in light water reactors. Academic Press, USA, pp. 425–517.10.1016/B978-0-12-388446-6.00005-8Search in Google Scholar
Kuntoro, I., Sriyono, M., Sunaryo, G., Rokhim, A., Taxwim, and Sukmana, J. (2019). Overview of the application of the specific safety requirements to BATAN research reactors overview of the application of the specific safety requirements to BATAN research reactors. J. Phys. Conf., https://doi.org/10.1088/1742-6596/1198/2/022064.Search in Google Scholar
Lestari, D., Sunarko, S. and Utomo, S.B. (2016). Ion exchange resin waste analysis of primary coolant purification system of RSG-GAS. In: Proceeding of 7-th national seminar on radwaste technology management, pp. 62–66.Search in Google Scholar
Li, J., Chen, L., and Wang, J. (2021). Solidification of radioactive wastes by cement-based materials. Prog. Nucl. Energy 141: 103957, https://doi.org/10.1016/j.pnucene.2021.103957.Search in Google Scholar
Lin, C.C. (1996). Radiochemistry in nuclear power reactors. NAS-NS-311. In: N. Radiochemistry. National Academies Press, Washington.Search in Google Scholar
Luhur, N., Subiharto, S., Muslimu, F.A., and Hartoyo, U. (2013). Radiation safety evaluation of rabbit system of RSG-GAS. In: Proceeding of National seminar on nuclear facility management. PTAPB-BATAN, Yogyakarta, pp. 473–480.Search in Google Scholar
PRSG-BATAN (2020). Safety analysis report of RSG-GAS 2020 Rev.11, chapter XII: safety of operational radiology. In: SAR RSG GAS Versi 11. RSG-GAS, pp. 1–115.Search in Google Scholar
Rahayu, D.S. and Aji, D. (2016). Nuclear fuel cladding integrity detection by using Sipping Test. In: Proceeding of national seminar on radwaste management XIV, pp. 186–193.Search in Google Scholar
Ratnawati, E. and Lestari, D.E. (2018). Study of primary coolant impurities in reactor RSG-GAS after 30 years of operation. Ganendra 4: 17–24, https://doi.org/10.17146/gnd.2018.21.1.3675.Search in Google Scholar
Seidel, F.J. (2020). Chemical composition aluminum alloys. In: DIN Germany. Total Materia, Swiss, pp. 3–4.Search in Google Scholar
Setyawan, A., Darmawan, A., and Purnomo, S. (2016). Liquid radwaste treatment analysis by using ion exchange column. Buletin Limbah 13: 1–9.Search in Google Scholar
Sindelar, R.L., Chandler, G.T., and Mickalonis, J.I. (2011). Water quality and corrosion: considerations for nuclear reactor systems. J. S. C. Acad. Sci. 9: 43–46.Search in Google Scholar
Sriyono, S., Kusumastuti, R., Butarbutar, S.L., Hafid, A., Sunaryo, G.R., Lestari, D.E., and Ratnawati, E. (2016). The debris particles analysis of RSG GAS coolant to anticipate sediment induced corrosion. Jurnal Pengembangan Energi Nuklir 18: 11, https://doi.org/10.17146/jpen.2016.18.1.2675.Search in Google Scholar
Sugito, B., Bernardi, Y., Budiyono, B., and Masudi, M. (2018). Liquid radwaste treatment by evaporation method. In: Proceeding of Radwaste research PTLR 2012. PTLR-BATAN, Jakarta, pp. 111–117.Search in Google Scholar
Sunaryo, G.R., Kusumastuti, R., and Sriyono, S. (2021). Corrosion surveillance program for tank , fuel cladding and supporting structure of 30 MW Indonesian RSG GAS research reactor. Kerntechnik 86: 236–243, https://doi.org/10.1515/kern-2020-0083.Search in Google Scholar
Sundari, T., Darmawan, A., Arifin, A., Irzon, Y., Marhaeni, J.P., and Pudjiastuti, L.K. (2016). Integrity testing of spent fuel of RI-68, RI-190 and RI-187. REAKTOR – Nucl. React. Bull. 13: 54–65.Search in Google Scholar
Thinova, L., Frontasyeva, M., Vergel, K., and Bayushkina, E. (2014). Assessment of contamination with trace elements and man-made radionuclides around Temelin Nuclear Power Plant in Czech Republic. Radiat. Phys. Chem. 104: 432–435, https://doi.org/10.1016/j.radphyschem.2014.06.010.Search in Google Scholar
Trojanowicz, M., Kołacińska, K., and Grate, J.W. (2018). A review of flow analysis methods for determination of radionuclides in nuclear wastes and nuclear reactor coolants. Talanta 183: 70–82, https://doi.org/10.1016/j.talanta.2018.02.050.Search in Google Scholar PubMed
Vukanac, I., Đurašević, M., Nikolić, J.K., Pantelić, G., Rajačić, M., Janković, M., Sarap, N., and Todorović, D. (2021). Preparation and validation of laboratory radioactive standards for experimental calibration in gamma ray spectrometry. Radiat. Phys. Chem. 183: 1–7, https://doi.org/10.1016/j.radphyschem.2021.109407.Search in Google Scholar
Yusi, Y. and Muhammad, I. (2013). Operating management of RSG-GAS research reactor. In: Proceeding of national seminar on nuclear facility management, pp. 15–21.Search in Google Scholar
Supplementary Material
This article contains supplementary material (https://doi.org/10.1515/kern-2022-0113).
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