Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega
Vol 24, No 3 (2022): October 2022

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

Luqman Satria Pradana (Physics Department, Faculty of Mathematics and Natural Sciences (FMIPA), Universitas Sebelas Maret, Jl. Ir. Sutami No. 36A Kentingan, Jebres, Surakarta – Central Java, Indonesia 57126)
Utari Utari (Physics Department, Faculty of Mathematics and Natural Sciences (FMIPA), Universitas Sebelas Maret, Jl. Ir. Sutami No. 36A Kentingan, Jebres, Surakarta – Central Java, Indonesia 57126)
Suharyana Suharyana (Physics Department, Faculty of Mathematics and Natural Sciences (FMIPA), Universitas Sebelas Maret, Jl. Ir. Sutami No. 36A Kentingan, Jebres, Surakarta – Central Java, Indonesia 57126)
Azizul Khakim (Research Center for Nuclear Reactor Technology (PRTRN), Research Organization for Nuclear Energy (ORTN), National Research and Innovation Agency (BRIN), Building 80th Science and Technology Research Center (PUSPITEK), Serpong, Banten, Indonesia 15314)



Article Info

Publish Date
09 Nov 2022

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.

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Journal Info

Abbrev

tridam

Publisher

Subject

Energy Materials Science & Nanotechnology

Description

Jurnal Teknologi Reaktor Nuklir "TRI DASA MEGA" adalah forum penulisan ilmiah tentang hasil kajian, penelitian dan pengembangan tentang reaktor nuklir pada umumnya, yang meliputi fisika reaktor, termohidrolika reaktor, teknologi reaktor, instrumentasi reaktor, operasi reaktor dan lain-lain yang ...