MEASURED AND CALCULATED INTEGRAL REACTIVITY OF CONTROL RODS IN RSG-GAS FIRST CORE

Wahid Luthfi, Surian Pinem, Donny Hartanto, Lily Suparlina, Dwi Haryanto

DOI: http://dx.doi.org/10.17146/tdm.2022.24.1.6593

Abstract


The control rod worth is one of the important parameters for the operation of a nuclear reactor. Proper measurement and calculation of the control rod worth are essential for the safe reactor operation under normal and transient conditions that are initiated by a postulated event such as a stuck rod, control rods ejection, etc. This paper presents calculation results of integral reactivity of the RSG-GAS research reactor first core and its comparison with the experimental data. Calculations were performed using the continuous energy transport code Serpent 2 with ENDF/B-VIII.0 nuclear data. Integral reactivity measurement was done by compensating method with control rod bank, regulating rod, and reactivity meter. Calculations are carried out for each method used in control rod measurement data with an aim to validate calculated results to experimental data. Compared with the measured experiment data, there are no significant differences in calculation results of integral reactivity. The maximum difference of the control rod's total reactivity is 1.26% compared to the measurement carried out by compensating method with regulating rod.

Full Text:

PDF

References


  1. Torabi M., Lashkari A., Masoudi S.F., Bagheri S. Neutronic Analysis of Control Rod Effect on Safety Parameters in Tehran Research Reactor. Nucl. Eng. Technol. 2018. 50(7):1017–23.
  2. Yari M., Lashkari A., Masoudi S.F., Hosseinipanah M. Three Dimensional Analysis of Temperature Effect on Control Rod Worth in TRR. Nucl. Eng. Technol. 2018. 50(8):1266–76.
  3. Nasrazadani Z., Ahmadi A., Khorsandi J. Measurement of Safety Rods Reactivity Worth by Advanced Source Jerk Method in HWZPR. Nucl. Eng. Technol. 2019. 51(4):963–7.
  4. Surian P., Sembiring T.M., Tukiran S. Reactivity Insertion Accident Analysis During Uranium Foil Target Irradiation in the RSG-GAS Reactor Core. Nucl. Technol. Radiat. Prot. 2020. 35(3):1–7.
  5. Surbakti T., Pinem S., Suparlina L. Dynamic Analysis on the Safety Criteria of the Conceptual Core Design in MTR-type Research Reactor. Atom Indones. 2018. 44(2):89–97.
  6. 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):123–8.
  7. Shchurovskaya M. V., Alferov V.P., Geraskin N.I., Radaev A.I., Naymushin A.G., Chertkov Y.B., et al. Control Rod Calibration Simulation Using Monte Carlo Code for the IRT-type Research Reactor. Ann. Nucl. Energy. 2016. 96:332–43.
  8. Hartanto D., Liem P.H. Analysis of the First Core of the Indonesian Multipurpose Research Reactor RSG-GAS Using the Serpent Monte Carlo Code and the ENDF/B-VIII.0 Nuclear Data Library. Nucl. Eng. Technol. 2020. 52(12):2725–32.
  9. 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.
  10. Surbakti T., Pinem S., Sembiring T.M., et.al. Calculation of Control Rods Reactivity Worth of RSG-GAS First Core Using Deterministic and Monte Carlo Methods. Atom Indones. 2019. 45(2):69–79.
  11. Liem P.H., Zuhair, Hartanto D. Sensitivity and Uncertainty Analysis on the First Core Criticality of the RSG GAS Multipurpose Research Reactor. Prog. Nucl. Energy. 2019. 114(February):46–60.
  12. Leppänen J. et al. The Serpent Monte Carlo Code: Status, Development and Applications in 2013. Ann. Nucl. Energy. 2015. 82:142–150.
  13. Sembiring T.M., Pinem S., Hartanto D., Liem P.H. Analysis of the Excess Reactivity and Control Rod Worth of RSG-GAS Equilibrium Silicide Core Using Continuous-Energy Monte Carlo Serpent2 Code. Ann. Nucl. Energy. 2021. 154:108107.


Refbacks

  • There are currently no refbacks.


PTKRN Digital Library Mendeley