Estimation of Neutron and Prompt Photon Dose Rate Distribution in TMSR-500 Using MCNP6

Authors

  • Luqman Satria Pradana Physics Department, Faculty of Mathematics and Natural Sciences, Universitas Sebelas Maret
  • Utari Physics Department, Faculty of Mathematics and Natural Sciences, Universitas Sebelas Maret
  • Suharyana Physics Department, Faculty of Mathematics and Natural Sciences, Universitas Sebelas Maret
  • Azizul Khakim National Research Innovation Agency (BRIN)

DOI:

https://doi.org/10.17146/tdm.2022.24.3.6692

Keywords:

Neutron and Prompt Photon, Dose Rate Distribution, MCNP6, TMSR-500

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.

References

Gehin J.C., Powers J.J. Liquid Fuel Molten Salt Reactors for Thorium Utilization. Nucl. Technol. 2016. 194(2):152-61.

https://doi.org/10.13182/NT15-124

Buckthorpe D. Introduction to Generation IV Nuclear Reactors. Struct. Mater. Gener. IV Nucl. React. 2017.:1-22.

https://doi.org/10.1016/B978-0-08-100906-2.00001-X

Devanney J., Jorgensen L., Livingston J., Moir R., Rodenburg A.C., Uhlik C. ThorCon the Do-able Molten Salt Reactor Design Control Document. 2015.

BAPETEN Peraturan Kepala Badan Pengawas Tenaga Nuklir Repulik Indonesia. Perka BAPETEN. 2013. 4 Thn 2013:1-29.

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)

https://doi.org/10.1007/s41365-018-0396-y

Schön J.H. Nuclear/Radioactive Properties. 2015.

https://doi.org/10.1016/B978-0-08-100404-3.00005-6

Obodovskiy I. Neutron Sources. Radiation. 2019.:289-92.

https://doi.org/10.1016/B978-0-444-63979-0.00019-7

De Sanctis E., Monti S., Ripani M. Energy from Nuclear Fission: An Introduction. Cham:Springer International Publishing AG; 2016.

https://doi.org/10.1007/978-3-319-30651-3

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.

https://doi.org/10.1016/j.jrras.2018.04.002

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.

https://doi.org/10.12943/CNR.2016.00030

Fisher D.R., Fahey F.H. Appropriate Use of Effective Dose in Radiation Protection and Risk Assessment. Health Phys. 2017. 113(2):102-9.

https://doi.org/10.1097/HP.0000000000000674

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.

https://doi.org/10.1080/00295450.2020.1720557

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)

https://doi.org/10.1088/1742-6596/1153/1/012111

Khakim A., Rhoma F., Waluyo A., Suharyana S. The neutronic Characteristics of Thermal Molten salt Reactor. AIP Conf. Proc. 2021. 2374

https://doi.org/10.1063/5.0058949

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.

https://doi.org/10.1016/j.radphyschem.2017.10.007

Amptek X-Ray Fluorescence (XRF): Understanding Characteristic X-Rays. 2016.:1-6.

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Published

2022-11-09

How to Cite

Pradana, L. S., Utari, Suharyana, & Khakim, A. (2022). Estimation of Neutron and Prompt Photon Dose Rate Distribution in TMSR-500 Using MCNP6. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, 24(3), 107–116. https://doi.org/10.17146/tdm.2022.24.3.6692