CALCULATION OF RADIOACTIVE SOURCE TERM RELEASE FROM FLEXBLUE NPP

Muhammad Budi Setiawan, Pande Made Udiyani

DOI: http://dx.doi.org/10.17146/tdm.2021.23.2.6254

Abstract


One of the National Research Programs (PRN) in the energy sector of the Indonesian Ministry of Research and Technology for the period of 2020-2024 is small modular reactor (SMR) nuclear power plant (NPP) assessment. The France’s Flexblue is a PWR-based SMR submerged reactor with a power of 160 MWe. The Flexblue reactor module was built on the ocean site and easily provided the supply of reactor modules, in accordance with the conditions of Indonesia as an archipelagic country. Therefore, it is necessary to know the release of fission products (source term), which is necessary for the study of the radiation safety of a nuclear reactor. This paper aims to examine the source term in normal operating conditions and abnormal normal operating conditions, as well as postulated accidents. Based on the Flexblue reactor core parameter data, the calculation of the reactor core inventory uses the ORIGEN2 software is previously evaluated. The source term calculation uses a mechanistic approach and a graded approach. The normal source term is calculated assuming the presence of impurities on the fuel plate, due to fabrication limitations. Meanwhile, the abnormal source term is postulated in the LOCA event. The core reactor inventory and source term is divided into 8 radionuclide groups which are Noble gasses group (Xe, Kr); Halogen (I); Akali Metal (Cs, Rb); Tellurium Group (Te, Sb, Sc); Barium-Strontium Group (Ba, Sr); Noble Metals (Ru, Rh, Pd, Mo, Tc, Co); Lanthanides group (La, Zr, Nd, Eu, Nb, Pm, Pr, Sm, Y, Cm, Am) and Cerium Group (Ce, Pu , Np).


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References


  1. Kuntjoro S., Setiawan M.B., Udiyani P.M, Husnayani I, Radionuclide Inventory Analysis of The Flexblue Small Modular Reactor, AIP Conference Proceedings. 2019. 2180, 020006.
  2. Santinello M., Ricotti M.E., Ninokata H., Haratyk G., Ingremeau J.J., Gourmel V. External Heat Transfer Capability of A Submerged SMR Containment: The Flexblue Case, Progress in Nuclear Energy. 2017. 96: 62-75.
  3. Udiyani P.M. and Setiawan M.B. Source term Assessment for 100 MWe Pressurized Water Reactor. Journal of Nuclear Reactor Technology Tri Dasa Mega. 2020. 22 (2): 61-67.
  4. Udiyani PM., Husnayani I., Setiawan M.B., Kuntjoro S., Adrial H., Hamzah A. Estimation of Radioactive Source Term From RDE Accident. Journal of Nuclear Reactor Technology Tri Dasa Mega. 2019. 21 (3): 113-118.
  5. Zhao Y., Zhang L.,Tong J. Development Of Rapid Atmospheric Source Term Estimation System For AP 1000 Nuclear Power Plant. Progress in Nuclear Energy. 2015. 81: 264-275.
  6. Herranza L.E., Hasteb T., Kärkeläc T. Recent Advances in The Source Term Area Within The SARNET European Severe Accident Research Network. Nuclear Engeneering and Design. 2015. 288: 56-74.
  7. Udiyani P.M., Husnayani I., Deswandri, Sunaryo GR. Analysis of Radiation Safety for Small Modullar Reactor (SMR) on PWR 100 MWe type in: International Symposium of Emerging Nuclear Technology and Engineering Novelty. IOP Conf. Series: Journal of Physics: Conf. Series. 2018. 962, 012035.
  8. Udiyani P.M., Kuntjoro S., Sunaryo G.R, Susiati H. Atmospheric Dispersion Analysis for Expected Radiation Dose due to Normal Operation of RSG-GAS and RDE Reactors. AJI. 2018. 44 (3): 115-121.
  9. Winiarek A., et al. Estimation Of Cesisium 137 Source Term From Fukushima Daiichi Nuclear Power Plant Using A Joint Consistent Assimilation Of Air Concentration And Deposition Observations. Atmospheric Environment. 2014. 82: 268-279.
  10. Shoppner M., et al. Estimation Of Time Defendant Radioactive Source Term From The Fukusima Nuclear Power Plant Accident Using Atmospheric Transport Modeling. Journal of Environmental Radioactivity. 2012. 14: 10-14.
  11. Guo Q. Prelimanary Source Term And Consequences Assesment Of Primary Cover Gas Leakage Accidentfor CLEAR. Progress in Nuclear Energy. 2015. 78: 136-140
  12. Mehbooba K., Park K., Khan R. Quantification Of In-Containment Fssion Products Source Term For 1000 MWe PWR Under Loss of Coolant Accident. Annals of Nuclear Energy. 2015. 75: 365-376.
  13. Udiyani PM., Husnayani I., Setiawan M.B., Kuntjoro S., Adrial H., Hamzah A. Estimation of Radioactivity Impact For RDE Based on HTR-10 Hypthetical Accident- A Case Study. in: International Symposium of Emerging Nuclear Technology and Engineering Novelty. IOP Conf. Series: Journal of Physics: Conf. Series. 2019. 022037.
  14. Vismes Otta A., Gurriarana R., Cagnata X., Massonb O. Fission Product Activity Ratios Measured at Trace Level over France During The Fukushima Accident. Journal of Environmental Radioactivity. 2013. 125: 6-16.
  15. Vandenhovea H., et al. Predicting The Environmental Risks Of Radioactive Discharges From Belgian Nuclear Power Plants. Journal of Environmental Radioactivity. 2013. 126: 61-76.
  16. Setiawan, M.B., Kuntjoro S., Udiyani P.M., Husnayani I., Evaluation Of Radionuclide Inventory in The CAREM-25 Small Modular Reactor, AIP Conference Proceedings. 2019. 2180, 020009.
  17. Mehboob K., Xinrong C., Source Term Evaluation of Two Loop PWR Under Hypothetical Severe Accidents, Annals of Nuclear Energy. 2012. 50: 271-284
  18. Setiawan, M.B., Udiyani, P.M., Kuntjoro S.,Husnayani I., Tukiran S., Analysis on Transmutation of Long-Lived Fission Products from PWR Spent Fuel Using the 30-MW(thermal) RSG-GAS Reactor, Nuclear Tehcnology. 2020. 206: 1945-1950
  19. Muswemaa J.L., Ekokoa G.B., Lukanda V.M., Loboa J.K.-K, Darko E.O., Boafo E.K., Source Term Derivation and Radiological Safety Analysis for The TRICO II Research Reactor In Kinshasa, Nuclear Engineering and Design. 2015. 281: 51-57
  20. Ozaa R.B., Indumatia S.P., Puranika V.D., Sharmab D.N., Ghoshb A.K. Simplified Approach for Reconstructing The Atmospheric Source Term For Fukushima Daiichi Nuclear Power Plant Accident Using Scanty Meteorological Data. Annals of Nuclear Energy. 2013. 58: 95-101.


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