Neutrons and Gamma-Ray Dose Calculations in Subcritical Reactor Facility Using MCNP

Xoubi, Ned

doi:10.3390/atoms4030020

Cited by 7 publications

(3 citation statements)

References 11 publications

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“…In order for the flux value to be converted into a dose, it used flux-to-dose rate conversion factors for photons and neutrons from ICRP-74 and ANSI/ANS [7,8]. The conversion factors are plotted on a log-log scale as recommended by the ICRP and ANSI, creating a straight line between any two points, for the proper interpolation between points [9].…”

Section: Resultsmentioning

confidence: 99%

Simulation of Neutron and Gamma Dose Rate of The TRIGA 2000 Reactor Using Monte Carlo Method

Rakotovao

Permana

Oetami

et al. 2022

J. Phys.: Conf. Ser.

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The neutron and gamma radiation doses were calculated from the operation of the 1 MW TRIGA 2000 Reactor in a simulation using the Monte Carlo method with MCNPX and PHITS program. Simulation is done by modelling the geometry of the reactor component materials and running it on a computer. The radiation source in the form of a fission reaction in the reactor core has been simulated using MCNPX to produce a dose of neutron and gamma radiation in the TRIGA 2000 core. Attenuation of neutron and gamma radiation by the reactor building is simulated using the PHITS code so that the neutron and gamma dose rates are obtained on the source, y, and z from reactor core. Interpolation of dose rate curves on large material thicknesses was carried out with the TVL neutron and gamma values of the simulation results for each reactor material. The simulation results shows that the gamma neutron dose rate outside the TRIGA 2000 reactor building is still below the dose limit value for radiation workers.

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Section: Resultsmentioning

confidence: 99%

Simulation of Neutron and Gamma Dose Rate of The TRIGA 2000 Reactor Using Monte Carlo Method

Rakotovao

Permana

Oetami

et al. 2022

J. Phys.: Conf. Ser.

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“…The conversion factor for thermal neutron with energy 0.025 is 4.14×10 -3 (mrem.h -1 per n.cm -2 .sec -1 ) [19,20]. The absorbed doses for 2 sec.…”

Section: Methodsmentioning

confidence: 99%

The structure, and magnetic properties of NiR0.05Fe1.95O4 (rare earth R=Sm, Gd): Effect of Thermal Neutron Radiation

Roumaih

Elbahrawy

Ismail

2021

Arab Journal of Nuclear Sciences and Applications

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“…gives the gamma component and can be used to calculate the thermal neutron response on the other detector [17]. Furthermore, computational tools using the Monte Carlo method were used by some authors to estimate the deposited dose on TL detectors [64,81,82].…”

Section: Detection Of Neutrons In a Nuclear Research Reactormentioning

confidence: 99%

Production of synthetic polycrystals of CaSiO3 and their study as new detectors of gamma radiation, thermal neutrons and accelerated ions.

Lorenzo¹

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Em especial ao prof. Shigueo Watanabe pela sua orientação, paciência, disposição e apoio no desenvolvimento deste trabalho, incentivando a maioria das minhas decisões, agradeço muito. Ao Conselho Nacional de desenvolvimento Científico e Tecnológico (CNPq) pelo apoio financeiro. À Eng. Elizabeth Ribeiro Somessari, ao Eng. Carlos Gaia da Silveira do CTR-IPEN-SP; ao Aldo Oliveira e Vicente de Paulo Campos do GMR-IPEN-SP pelas inúmeras vezes que nos atenderam gentilmente para as irradiações gama realizadas neste trabalho. À Professora Carmen Cecilia Bueno do Centro de Tecnologia das Radiações-IPEN pela ajuda nas irradiações com nêutrons no reator nuclear de pesquisa IEA-R1 do IPEN. Ao Prof. Gundu Rao pela análise das medidas de EPR as quais ajudaram muito no aprimoramento do presente trabalho, e pela ajuda na revisão do inglês. Ao prof. Satoshi Kodaira do Instituto Nacional de Ciências Radiológicas (NIRS) em Chiba-Japão e à Dra. Luana Nascimento do Centro Belga de Pesquisa Nuclear (SCK•CEN) pela ajuda nas irradiações das nossas amostras com prótons e íons de carbono no NIRS. Ao Prof. Sergey Nikiforov e à colega Daria Ananchenko do Instituto de Física e Tecnologia da Universidade Federal dos Urais em Ecaterimburgo-Rússia por me aceitar no seu laboratório como parte de um estágio de pesquisa. ii Ao Dr. Tássio A. Cavalieri do Centro de Engenharia Nuclear do Instituto de Pesquisas Energéticas e Nucleares (CEN-IPEN-SP) pela importante colaboração e ajuda com as simulações de Monte Carlo. À Nancy Kuniko Umisedo do Laboratório de Dosimetria do IFUSP pelas irradiações com raios X. Aos Professores Nilo Cano, René Rojas e Fernando Chubaci pela paciência, compreensão e pela sua disponibilidade para responder às minhas dúvidas no desenvolvimento deste trabalho. À Dra. Roseli Gennari pela ajuda na mistura das amostras e pelas sugestões na produção dos policristais usados neste trabalho. À Edna Toledo pela ajuda e disposição nos processos burocráticos e os muitos momentos agradáveis na hora do café no LACIFID.

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Neutrons and Gamma-Ray Dose Calculations in Subcritical Reactor Facility Using MCNP

Cited by 7 publications

References 11 publications

Simulation of Neutron and Gamma Dose Rate of The TRIGA 2000 Reactor Using Monte Carlo Method

Simulation of Neutron and Gamma Dose Rate of The TRIGA 2000 Reactor Using Monte Carlo Method

The structure, and magnetic properties of NiR0.05Fe1.95O4 (rare earth R=Sm, Gd): Effect of Thermal Neutron Radiation

Production of synthetic polycrystals of CaSiO3 and their study as new detectors of gamma radiation, thermal neutrons and accelerated ions.

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