1. Home
  2. Volume 24 Nomor 1 Januari 2021
  3. Surbakti

COMPARISON OF MEASURED AND CALCULATED CONTROL ROD REACTIVITY OF THE RSG-GAS CORE

T. Surbakti(1), W. Luthfi(2), Purwadi Purwadi(3), D. Hartanto(4),


(1) Center for Nuclear Reactor Safety and Technology - National Nuclear Energy Agency (BATAN)
(2) Center for Nuclear Reactor Safety and Technology - National Nuclear Energy Agency (BATAN)
(3) Center of Multipurpose Reactor (PRSG) - National Nuclear Energy Agency (BATAN)
(4) Department of Mechanical and Nuclear - Engineering, University of Sharjah
Corresponding Author

Abstract


COMPARISON OF MEASURED AND CALCULATED CONTROL ROD REACTIVITY OF THE RSG-GAS CORE. The reactivity worth and a calibration curve of control rods are important physical parameters on account of the nuclear safety of the RSG-GAS reactor core. Reactivity characteristics of control rods must be determined not only, but also in the first criticality and also after any substantial changes in the reactor core. The required time to measure the reactivity worth by various methods depends mostly on the quality of the reactivity measurement devices. The rod-insertion method has some specific advantages which make such compensation unnecessary while yielding both integral and differential reactivity worth curves, as well as total reactivity worth. In this study, the total control rod worth of RSG-GAS is calibrated experimentally using a rod-insertion method to verify calculation results for the new core configuration. Calculations were done by diffusion and Monte Carlo methods using Batan-3DIFF and MCNP5 codes. Total control rod reactivity worth of the control rod is obtained 17.54 $,  17.03 $, and 17.87 $ by experiment,  Batan-3DIFF, and MCNP5 calculations, respectively. The relative difference between the experimental and calculated values of control rod reactivity worth is about 3.0 %, which indicates a good agreement between the applied experimental method and calculation.


Keywords


MCNP5, RSG-GAS reactor, Control rod, WIMSD-5B, BATAN-3DIFF

References


[1] Setiyanto and T. Surbakti. “Analysis of gamma heating at TRIGA mark reactor core Bandung using plate-type fuel,” Jurnal Tri Dasa Mega., vol. 18, no.3, pp. 127-134, 2016. http://dx.doi.org/10.17146/tdm.2016.1.3.30 04.

[2] M. Rahgoshaya, O. N. Kalkhoran, "Calculation of control rod worth and temperature reactivity coefficient of fuel and coolant with burn-up changes for VVRS-2 MWth nuclear reactor." Journal of Nuclear Engineering and Design., vol. 256, pp. 322-331, 2013. https://doi.org/10.1016/j.nucengdes.2012.08.033.

[3] T, Surbakti and T. M. Sembiring, "Neutronics analysis on mini test fuel in the RSG-GAS core," Jurnal Tri Dasa Mega., vol. 18, no.1, pp. 29-40, 2016. https://doi.org/10.17146/tdm.2016.18.1.2329

[4] T. Surbakti and M. Imron, "Fuel burn-up calculation for RSG-GAS working core." Jurnal Penelitian Fisika dan Aplikasinya., vol. 7, no. 2, pp. 89-101, 2017. http:/doi: 10.26740/jpfa.v7n2.p89-101.

[5] Rokhmadi dan T. Surbakti, "Effect of fuel density on reactivity coefficient parameter of the RRI core design," Jurnal Tri Dasa Mega., vol. 15, no. 2, pp. 77-89, 2013. Available from: http://jurnal.batan.go.id/index.php.tridam//article/view/1865.

[6] L. Suparlina, "RSG-GAS core conversion management of high loaded silicide fuels,". Jurnal Tri Dasa Mega., vol. 15, no. 3, pp. 137-149, 2013. Available from: http://jurnal. batan.go.id /index.php /tridam /article/ view/ 1860.

[7] T. Surbakti dan Purwadi, "Reactivity characteristic of the RSG-GAS working core for 30 years operation," Jurnal Penelitian Fisika dan Aplikasinya., vol. 7, no. 1, pp. 13-26, 2017. https://doi.org/10.26740/jpfa.v7n1.p13-26.

[8] T. Surbakti, S. Pinem, T. M. Sembiring, L. Suparlina , J. Susilo, "Neutronics conceptual design of the innovative research reactor core using uranium molybdenum fuel," Jurnal Tri Dasa Mega., vol. 3 no. 14, pp. 178-191, 2012. Available from: http://jurnal.batan.go.id/ index. php/ tridam/ article/view/1878.

[9] T. Surbakti, T. M. Sembiring, S. Pinem, "Analysis of silicide fuel density effect on the kinetic parameters of the RSG-GAS reactor core," Jurnal Penelitian Fisika dan Aplikasinya., vol. 3, no. 1, pp. 19-30, 2013. https://doi.org/10.26740/jpfa.v3n1.p19-30.

[10] Batan. Safety Analysis Report of RSG-GAS rev 10.1, 2011.

[11] L. P. Hong, "Development of an In-core fuel management code for serching equilibrium core in 2-D reactor geometry (Batan-equil-2D)," Journal Atom Indonesia., vol. 23, no. 1, pp. 1-19, 1997.

[12] S. Pinem, T. M. Sembiring, P. H. Liem. Neutronic and thermal-hydraulic safety analysis for the optimization the Uranium target in the RSG-GAS reactor. Journal of Atom Indonesia., vol. 42 no.3, pp. 123-128, 2016. DOI: dx.doi.org/10.17146/aij.2016.532.

[13] P.H. Liem, T. Surbakti, and S. Donny, "Kinetics parameters evaluation on the first core of the RSG GAS (MPR-30) using continuous energy Monte Carlo method.". Progress in Nuclear Energy., vol. 109, pp. 196-203, 2018. DOI:https://doi.org/10.1016/j.pnucene.2018.08.014.

[14] S. Pinem, P. H. Liem, T. M. Sembiring and T. Surbakti, "Fuel element burnup measurements for the equilibrium LEU silicide RSG GAS (MPR-30) core under a new fuel management strategy". Annals of Nuclear Energy., vol. 98, pp. 211-217, 2016. DOI:http://dx.doi.org/ 10.1016/j.anucene.2016.08.

[15] S. Pinem, T. M. Sembiring, T. Surbakti, G. R. Sunaryo, "Reactivity Coefficient Calculation for AP1000 Reactor Using the NODAL3 Code. Journal of Physics," Conference Series., vol, 962 no.1, 012057 DOI: http://iopscience.iop.org/article/10.1088/1742-6596/962/1/012057/meta 2018.

[16] S. Pinem, T. M. Sembiring, T. Surbakti, I. Kuntoro, "Neutronic Analysis on Irradiation of the Leu Electroplating Target in the RSG-GAS Reactor for Production of 99mo Radionuclide," GANENDRA Majalah IPTEK Nuklir,. vol. 21, no. 2, pp. 55-61, 2018. DOI: http://jurnal.batan.go.id/index.php/ganendra/article/view/4392.

[17] S. Pinem, T. Surbakti, T. M. Sembiring, "Core Design TRIGA2000 Bandung Using U3Si2Al Fuel Element MTR Type," Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir., vol. 24, no. 2, pp. 93-103, 2018. DOI:https://doi.org/10.17146/urania.2018.24.2.4302.

[18] S. Pinem, T. M. Sembiring, T. Surbakti, "Core conversion design study of TRIGA Mark 2000 Bandung using MTR plate type fuel element," International Journal of Nuclear Energy Science and Technology. vol. 12, no. 3, pp. 222-238, 2018. DOI: http://DOI: 10.1504/IJNEST.2018.095689.

[19] T. Surbakti, Purwadi, "Analysis of Neutronic Safety Parameters of the RSG-GAS Research Reactor at Serpong," Jurnal Penelitian Fisika dan Aplikasinya., vol. 9,no. 1, pp. 78-91, 2019. DOI: https://doi.org/10.26740/jpfa.v9n1.p78-91.

[20] T. Surbakti, S. Pinem, T. M. Sembiring, A. Hamzah, K. Nabeshima, "Calculation of Control Rods Reactivity Worth of RSG-GAS First Core Using Deterministic and Monte Carlo Methods.". Atom Indonesia., vol. 45, no. 2, pp. 69-79, 2019. DOI: https://doi.org/10.17146/aij.2019.810.


Full Text: PDF (Bahasa Indonesia)

DOI: 10.17146/gnd.2021.24.1.5948

Copyright (c) 2021 GANENDRA Majalah IPTEK Nuklir

Creative Commons License
This work is licensed under a Creative Commons Attribution-NonCommercial-ShareAlike 4.0 International License.