ESTIMATION OF NEUTRON AND PROMPT PHOTON DOSE RATE DISTRIBUTION IN TMSR-500 USING MCNP6

Luqman Satria Pradana, Utari Utari, Suharyana Suharyana, Azizul Khakim

DOI: http://dx.doi.org/10.17146/tdm.2022.24.3.6692

Abstract


Thorium Molten Salt Reactor-500 (TMSR-500), one of the Generation IV nuclear reactors, is designed by Thorcon International, Pte. Ltd, which is projected to be built in Indonesia. The reactor core is radially surrounded by B4C shielding, but not the upper part. As the silo hall sits above the reactor core and is accessible by reactor personnel, the dose rate must be calculated in the area to ensure the workers receive an annual dose below the acceptable limit. The dose rate from neutrons and photons as the result of fission reactions are the only sources to be calculated in this research, without taking the source from fission products into account. This research aims to obtain the dose rate distribution of neutrons and prompt photons using Monte Carlo code MCNP6. The reactor was assumed to operate at a nominal thermal power of 557 MWth. Dose rate calculation was obtained from flux Tally F4 and converted into dose rate using Dose Energy Dose Function (DEDF) factor. Conversion factors of flux to the dose were based on ICRP-21 and ANSI/ANS-6.1.1 1977. The result of the calculations showed that the distribution of neutron and prompt photon fluxes does not reach the silo hall.

Full Text:

PDF

References


  1. Gehin J.C., Powers J.J. Liquid Fuel Molten Salt Reactors for Thorium Utilization. Nucl. Technol. 2016. 194(2):152–61.
  2. Buckthorpe D. Introduction to Generation IV Nuclear Reactors. Struct. Mater. Gener. IV Nucl. React. 2017.:1–22.
  3. Devanney J., Jorgensen L., Livingston J., Moir R., Rodenburg A.C., Uhlik C. ThorCon the Do-able Molten Salt Reactor Design Control Document. 2015.
  4. BAPETEN Peraturan Kepala Badan Pengawas Tenaga Nuklir Repulik Indonesia. Perka BAPETEN. 2013. 4 Thn 2013:1–29.
  5. Ji R.M., Yu C.G., Li M.H., Yan R., Zou Y., Liu G.M. Study on Inherent Neutron Sources in MSR. Nucl. Sci. Tech. 2018. 29(4)
  6. Schön J.H. Nuclear/Radioactive Properties. 2015.
  7. Obodovskiy I. Neutron Sources. Radiation. 2019.:289–92.
  8. De Sanctis E., Monti S., Ripani M. Energy from Nuclear Fission: An Introduction. Cham:Springer International Publishing AG; 2016.
  9. Al Zain J., El Hajjaji O., El Bardouni T., Boukhal H. Deterministic Evaluation of Safety Parameters and Neutron Flux Spectra in the MNSR Research Reactor using DRAGON-4 code. J. Radiat. Res. Appl. Sci. 2018. 11(3):255–61.
  10. Nguyen T.S., Wang X., Yue S. Validations of Gamma Measurements in Research Reactors With MCNP Full-Reactor Models. CNL Nucl. Rev. 2017.:1–7.
  11. Fisher D.R., Fahey F.H. Appropriate Use of Effective Dose in Radiation Protection and Risk Assessment. Health Phys. 2017. 113(2):102–9.
  12. Rook J.C., Weber K.P., Corcoran E.C. Advanced MCNP Simulation of the Neutron and Photon Flux and Absorbed Dose Rates for the SLOWPOKE-2 Nuclear Reactor at the Royal Military College of Canada. Nucl. Technol. 2020. 206(12):1861–74.
  13. Erawati Fadli O., Suparmi S., Khakim A., Suharyana S., Riyatun R. Power and Neutron Flux Distribution Analysis in the RSG-GAS Reactor :Preliminary Study to Identify the Reactor Readiness as Power Ramp Test Facility (PRTF). J. Phys. Conf. Ser. 2019. 1153(1)
  14. Khakim A., Rhoma F., Waluyo A., Suharyana S. The neutronic Characteristics of Thermal Molten salt Reactor. AIP Conf. Proc. 2021. 2374
  15. İrim G., Wis A.A., Keskin M.A., Baykara O., Ozkoc G., Avcı A., et al. Physical, Mechanical and Neutron Shielding Properties of h-BN/Gd2O3/HDPE Ternary Nanocomposites. Radiat. Phys. Chem. 2018. 144:434–43.
  16. Amptek X-Ray Fluorescence (XRF): Understanding Characteristic X-Rays. 2016.:1–6.


Refbacks

  • There are currently no refbacks.


PTKRN Digital Library Mendeley