Pande Made Udiyani, Ihda Husnayani, Mohamad Budi Setiawan, Sri Kuntjoro, Hery Adrial, Amir Hamzah



The design process of Experimental Power Reactor (Reaktor Daya Eksperimental/RDE) has been carried out by BATAN for the last five years, adopting HTGR-type reactor with thermal power of 10 MW. RDE is designed with the reference of similar reactor, namely HTR-10. During this process, source term estimation is required to prove the safety of RDE design, as well as to fulfill the concept of As Low As Reasonably Achievable (ALARA) in radiation protection. The source term is affected by the magnitude of the radioactive substances released from the reactor core due to an accident. Conservative accident postulations on the RDE are water ingress and depressurization accidents. Based on these postulations, source term estimation was performed. It follows the mechanistic source term flow, with conservative assumptions for the radioactive release of fuel into the coolant, reactor building, and finally discharged into the environment. Assumptions for the calculation are taken from conservative removable parameters.The result of source term calculation due to the water ingress accident for Xe-133 noble gas is 8.97E+12 Bq, Cs-137 is 3.59E+07 Bq, and I-131 is 4.34E+10 Bq. As for depressurization accident, the source term activity for Xe-133 is 3.90E+13Bq, Cs-137 is 1.56E+07 Bq, and I-131 is 1.89E+10Bq. The source term calculation results obtained in this work shows a higher number compared to the HTR-10 source term used as a reference. The difference is possibly due to the differences in reactor inventory calculations and the more conservative assumptions for source term calculation.

Keywords: RDE, HTGR, Radioactive, Source term, accident

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  1. Kuntjoro S., Udiyani P.M. Analisis inventory Reaktor Daya Eksperimental Jenis Reaktor Gas Temperatur Tinggi. Urania. 2016. 22 (1):53–64.
  2. 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
  3. Husnayani I., and Udiyani P.M. Radionuclide Characteristic of RDE Spent Fuels. Tri Dasa Mega. 2018. 20 (2):69–76.
  4. Udiyani P.M. and Kuntjoro S. Estimation of Routine discharge of radionuclides on Power Reactor Experimental RDE. Urania. 2017. 23 (1):45–51.
  5. Udiyani PM., Kuntjoro S., Setiawan M.B., Husnayani I. 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 1198 (2019) 022037
  6. Zhang Z., Wu z., Wang D.Current status and technical description of Chinese 2×250MWth HTR-PM demonstration plant. Nuclear Engineering and Design. 2009.239:1212–1219.
  7. Thomas S.The Pebble Bed Modular Reactor: An obituary. Energy Policy. 2011. 39:2431–2440.
  8. Verfonderna K.,Cao J., Liu T., Conclusion from V&V studies on the German codes PANAMA and FRESCO for HTGR fuel performance and fision product release. Nuclear Engineering and Design. 2014. 271:84-91.
  9. Shohei Uetaa S., Aiharaa J., Sawaa K., Yasudab A., Hondab M., Furihatab N.Development of high temperature gas-cooled reactor (HTGR) fuel in Japan. Progress in Nuclear Energy. 2011. 53:788–793.
  10. Yuanzhong L., Jianzhu C.Fission product release and its environment impact for normal reactor operations and for relevant accidents. Nuclear Engineering and Design. 2002.218: 81–90
  11. INL/EXT-10-17997 Mechanistic Source Terms White PaperIdaho National Laboratory, July 2010
  12. Ohashi H., Sato H., Tachibana Y., Kunitomi K., Ogawa M. Feasibily study on naturally safe HTGR (NSHTR) for air ingress accident. Nuclear Engineering and Design. 2014.271:537–544.
  13. Chen H.,Li C., Xing, H., Fang C. The R&D of HTR-STAC Program Package: Source Term Analysis Codes for Pebble-Bed High-Temperature Gas-Cooled Reactor.Hindawi Science and Technology of Nuclear Installations. 2018. Article ID 7389121, 9 pages
  14. Jeong H., Jeong Y.H., Chang S.H.. Comparison of two irradiation testing results of HTR-10 fuel spheres. Nuclear Engineering and Design. 2009.239:1066–1075.
  15. Van Roojen I.J., Duzzik M.L., Van Roojen P.M.Silver (Ag) transport in TRISO coated particel : A critical review. Nuclear Engineering and Design. 2014.271:180–188.
  16. Bombonia E., Cerulloa, N., Lomonaco G.Simplified models for pebble-bed HTR core burn-up calculations with Monteburns2.0. Annals of Nuclear Energy.2012. 40: 72–83.
  17. Powersa J.J., Wirthb B.D.A review of TRISO fuel performance models. Journal of Nuclear Materials.2010. 405: 74–82.
  18. Xhonneux A., Allelein H.J. Development of integrated fission product release and transport code for spatially resolved full-corecalculations of V/HTRs. Nuclear Engineering and Design. 2014.271:361–369.
  19. Verfonderna K. , Xhonneuxa A., Nabielekb H., Alleleina H.J. Computational analysis of modern HTGR fuel performance and fission product release during the HFR-EU1 irradiation experiment.Nuclear Engineering and Design. 2014. 271:385-7120
  20. Takamatsu K., Yan X.L., Nakagawa S., Sakaba N., Kunitomi, K. Spontaneous stabilization of HTGRs without reactor scram and core cooling. Nuclear Engineering and Design. 2014.271:379-387
  21. Sato H.,Ohashi H., Tachibana Y., Kunitomi K., Ogawa M. Feasibily study on naturally safe HTGR (NSHTR) for air ingress accident. Nuclear Engineering and Design. 2014.271:530–536
  22. Herranz L.E., Fontanet J.,Analysis of the effect of water ponds on HTR confinement behavior under accident conditions.Progress in Nuclear Energy.2013. 67:7-14


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