Proceedings of the First National Seminar Universitas Sari Mulia, NS-UNISM 2019, 23rd November 2019, Banjarmasin, South Kalimantan, Indonesia

Research Article

Neutron Flux Parameter for In-Vivo testing Boron Neutron Capture Therapy (BNCT) on Radial Piercing Beam Port Kartini Nuclear Reactor by Monte Carlo N-Particle Extended (MCNPX) Simulation Method

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  • @INPROCEEDINGS{10.4108/eai.23-11-2019.2298332,
        author={Ikna Urwatul Wusko and Nur  Hidayah},
        title={Neutron Flux Parameter for In-Vivo testing Boron Neutron Capture Therapy (BNCT) on Radial Piercing Beam Port Kartini Nuclear Reactor by Monte Carlo N-Particle Extended (MCNPX) Simulation Method },
        proceedings={Proceedings of the First National Seminar Universitas Sari Mulia, NS-UNISM 2019,  23rd November 2019, Banjarmasin, South Kalimantan, Indonesia},
        publisher={EAI},
        proceedings_a={NS-UNISM},
        year={2020},
        month={7},
        keywords={neutron flux bnct kartini nuclear reactor in vivo testing},
        doi={10.4108/eai.23-11-2019.2298332}
    }
    
  • Ikna Urwatul Wusko
    Nur Hidayah
    Year: 2020
    Neutron Flux Parameter for In-Vivo testing Boron Neutron Capture Therapy (BNCT) on Radial Piercing Beam Port Kartini Nuclear Reactor by Monte Carlo N-Particle Extended (MCNPX) Simulation Method
    NS-UNISM
    EAI
    DOI: 10.4108/eai.23-11-2019.2298332
Ikna Urwatul Wusko1,*, Nur Hidayah2
  • 1: Industrial Engineering Study Programof Science and Technology Faculty Sari Mulia University,Indonesia
  • 2: Information System Study Program of Science and Technology Sari Mulia University,Indonesia
*Contact email: iknaurwatul@gmail.com

Abstract

The research of neutron flux parameters for in vivo testing BNCT on radial piercing beamport Kartini Nuclear Reactor was carried out using the MCNPX simulation method. BNCT is an alternative type of nuclear therapy that utilizes a 10B (n, α) 7Li reaction that produces a total kinetic energy of 2.79 MeV. Linear Energy Transfer (LET) of α particles and 7Li recoil will be deposited locally in the range of 5-9 µm. The determination of neutron flux was carried out after optimizing the collimator through the translucent port of the Kartini Reactor with a neutron source according to the output of the collimator. Neutron flux obtained after irradiation with an optimum concentration of boron 10 was 47 g of output data tumors for skin tissue.