ASSESSMENT OF OPERATION SAFETY OF THE RSG-GAS REACTOR TO SERVE RADIOISOTOPE TARGET IRRADIATION

Iman Kuntoro, Lily Suparlina, Purwadi Purwadi

DOI: http://dx.doi.org/10.17146/tdm.2022.24.2.6634

Abstract


The RSG-GAS multipurpose reactor is operated to serve the utilization in the field of radioisotope production and NAA, material research. The reactor actually has power of 30 MW thermal, but upon considerations of efficiency and of most users requirements, the reactor is mostly operated at the power of 15 MW thermal, 5 days a week to produce a primary radioisotope from target of 2 grams U-235. To guarantee the safe operation and optimum utilization, a safety procedure was established. The paper is intended to assesst the operation safety in serving radioisotope target irradiation at its cycle operation. Assessment was carried out for core numbers 102 – 105. The result shows that excess reactivity and shutdown margin reactivity are safe to provide the target irradiation in the core for each cycle operation. 

Full Text:

PDF

References


  1. PRSG BATAN, Safety Analysis Report RSGGAS Rev. 11, 2018
  2. Kuntoro I., Pinem S., Sembiring T. M., Haryanto D., and Purwanto S. Evaluation of Equilibrium Core Operation of the RSG-GAS Reactor. J. Teknol. Reakt. Nukl. Tri Dasa Mega. 2021. 23:15-20.
  3. Pinem S., Sembiring T.M. Accuracy of Batan3DIFF and MCNP6 Codes for Thermal Neutron Flux Distribution at the Irradiation Position of RSG-GAS Reactor. International Journal of Nuclear Energy Science and Technology. 2019. 13(4):295–312.
  4. Hedayat A. Conceptual Analyses of Equilibrium Conditions to Determine a Longterm Fuel Management Strategy for Research Reactors. Progress in Nuclear Energy. 2014. 71:61–72.
  5. Nissan E. An Overview of AI Methods for Incore Fuel Management: Tools for the Automatic Design of Nuclear Reactor Core Configurations for Fuel Reload, (Re)arranging New and Partly Spent Fuel. Designs. 2019. 3(3):1–45.
  6. Pinem S., Liem P.H., Sembiring T.M., Surbakti T. Fuel Element Burnup Measurements for the Equilibrium LEU Silicide RSG GAS (MPR-30) Core under a New Fuel Management Strategy. Annals of Nuclear Energy. 2016. 98
  7. Pinem S., Sembiring T.M., Liem P.H. Neutronic and Thermal-Hydraulic Safety Analysis for the Optimization of the Uranium Foil Target in the RSG-GAS Reactor. Atom Indonesia. 2016. 42(3):123–8.
  8. PRSG-BATAN, Safety Analyses of Iridium Target Irradiation and FPM (6 g) in the Core of RSG-GAS. Rev. 1, 2018.
  9. PRSG BATAN, Standard Operating Procedure for Acceptance of Irradiation Target, 2018.
  10. PRSG BATAN, Safety Assessment of Gd2O3 Target Irradiation, 2012.
  11. PRSG BATAN, Safety Assessment of SnO2 Target Irradiation, 2012
  12. PRSG-BATAN, RSG-Batan Operation Report Core No.102-104, of the RSG-GAS Reactor, 2021
  13. PRSG-BATAN, RSG-Batan Operation Report Core No. 105 of the RSG-GAS Reactor, 2022
  14. Hastuti, E. P., Kuntoro, I., Suwoto, S., Syarip, S., Basuki, P., Surbakti, T., Sudarmono, S. Map of Radioisotope Production and Batan Research Reactor Utilization. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, 2021 23(3), 105-114.
  15. Pinem S., Sembiring T.M., Surbakti T. Core Conversion Design Study of TRIGA Mark 2000 Bandung using MTR Plate Type Fuel Element. Int. J. Nucl. Energy Sci. Technol. 2018. 12(3):222-238.
  16. Surbakti T., Purwadi P. Analysis of Neutronic Safety Parameters of the Multi-Purpose Reactor–Gerrit Augustinus Siwabessy (RSGGAS) Research Reactor at Serpong. J. Penelit. Fis. dan Apl. 2019. 9(1):78-91.
  17. Liem P.H., Surbakti T., Hartanto D. Kinetics Parameters Evaluation on the First Core of the RSG GAS (MPR-30) using Continuous Energy Monte Carlo Method. Prog. Nucl. Energy. 2018. 109(June):196–203.
  18. Dawahra S., Khattab K., Saba G. Extending the Maximum Operation Time of the MNSR Reactor. Appl. Radiat. Isot. 2016. 115:256- 261.
  19. Dawahra S., Khattab K., Saba G. Calculation and Comparison of Xenon and Samarium Reactivities of the HEU, LEU Core in the Low Power Research Reactor. Appl. Radiat. Isot. 2015. 101:27–32.
  20. Surbakti T., Pinem S., Suparlina L. Dynamic Analysis on the Safety Criteria of the Conceptual Core Design in MTR-type Research Reactor. Atom Indonesia. 2018. 44(2):89-97.
  21. Surbakti T., Pinem S., Sembiring T.M., Hamzah A., Nabeshima K. Calculation of Control Rods Reactivity Worth of RSG-GAS First Core using Deterministic and Monte Carlo Methods. Atom Indones. 2019. 45(2):69–79.
  22. Pinem S., Sembiring T.M., Liem P.H. Neutronic and Thermal-hydraulic Safety Analysis for the Optimization of the Uranium Foil Target in the RSG-GAS Reactor. Atom Indones. 2016. 42(3):123–128.
  23. Surbakti T., Pinem S., Sembiring T.M., Subekti M., Sunaryo G.R. Preliminary Study for Alternative Conceptual Core Design of the MTR Research Reactor. J. Phys. Conf. Ser. 2018. 962(1).
  24. Surbakti T., Imron M. Fuel Burn-up Calculation for Working Core of the RSGGAS Research Reactor at Batan Serpong. J. Penelit. Fis. dan Apl. 2017. 7(2):89-101.
  25. Hedayat A. Benchmarking Verification of the Control Rod Effects on the MTR Core Parameters using the MTR-PC and MCNP Codes throughout 3D Core Modeling and Roddrop Experiment. Prog. Nucl. Energy. 2016. 88:183-190.
  26. Liu Z., Smith K., Forget B. Calculation of Multi-group Migration Areas in Deterministic Transport Simulations. Ann. Nucl. Energy. 2020. 140:107-110.
  27. Wang C., Liu L., Liu M., Zhang D., Tian W., Qiu S., et al. Conceptual Design and Analysis of Heat Pipe Cooled Silo Cooling System for the Transportable Fluoride-salt-cooled Hightemperature Reactor. Ann. Nucl. Energy. 2017. 109
  28. Villarino E.A., Mochi I. Thermal-hydraulic Models for Neutronic and thermaly- hydraulic Feedback in Citvap Code. 2014. 23:23-36.
  29. Pinem S., Surbakti T., Sembiring T. Optimization of Radioisotope Production at RSG-GAS Reactor using Deterministic Method. Journal Teknologi Indonesia 2016. 1 (2):12-18.
  30. Valtavirta V., Leppänen J., Viitanen T. Coupled Neutronics–fuel Behavior Calculations in Steady State using the Serpent 2 Monte Carlo Code. Ann. Nucl. Energy. 2017. 100.


Refbacks

  • There are currently no refbacks.


PTKRN Digital Library Mendeley