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All Journal Indonesian Journal of Physics (IJP) AME (Aplikasi Mekanika dan Energi) : Jurnal Ilmiah Teknik Mesin
Prastowo, Dian Adi
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Astronomy Computer Science & IT Control & Systems Engineering Earth & Planetary Sciences Electrical & Electronics Engineering Energy Engineering Mechanical Engineering Other

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ANALISIS KESELAMATAN RADIASI PERSONEL KENDARAAN TAKTIS DENGAN BODI BERBAHAN ARMOUR MENGGUNAKAN CODE MCNPX Kasmudin; Isnaini, Ismet; Sulistyo, Jos Budi; Yanto, Ausatha Rabbany; Subhiyah, Hana; Tukiman; Prastowo, Dian Adi; Syawaludin, Beny; Rezon, Kevin; Sanda; Fauzan, Azka Rizqi; Fauzi, Amal; Waluyo, Roy
AME (Aplikasi Mekanika dan Energi): Jurnal Ilmiah Teknik Mesin Vol. 10 No. 1 (2024)
Publisher : Universitas Ibn Khaldun Bogor

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.32832/ame.v10i1.561

Abstract

Kendaraan CBRN (Chemical, Biological, Radiological, and Nuclear) didesain untuk beroperasi dalam kondisi lingkungan berbahaya dan penuh risiko sehingga personel yang mengoperasikannya atau bekerja didalamnya harus dilindungi dari potensi bahaya CBRN, khususnya dari bahaya radiasi sinar gamma. BRIN bekerja sama dengan PT Pindad mengembangkan desain prototipe kendaraan taktis CBRN dengan bodi berbahan armour. Penelitian ini bertujuan untuk menganalisis keselamatan personel di dalam kendaraan taktis CBRN dengan bodi berbahan armour baja Secure 600 setebal 8 mm terhadap laju dosis serap efektif radiasi gamma yang dipancarkan Co-60 atau Cs-137 dengan cara pemodelan dan simulasi menggunakan code MCNPX. Hasil simulasi berupa nilai laju dosis serap efektif detektor yang dipasang di beberapa titik menggunakan tally F5 MCNPX di dalam kendaraan dan hasilnya dibandingkan dengan nilai batas dosis untuk pekerja radiasi. Secara umum dinding kendaraan taktis CBRN dari baja Secure 600 setebal 8 mm untuk kuat sumber Co-60 atau Cs-137 sampai 1 mCi menghasilkan laju dosis aman, sedangkan untuk kuat sumber di atas 1 mCi tidak aman bagi personel di dalam kendaraan CBRN. Penemuan ini sangat penting dalam desain dan pengembangan kendaraan taktis CBRN yang memberi perlindungan maksimum bagi personel di dalamnya terhadap paparan radiasi sinar gamma.  
Design of Neutron Activation and Radiography Facilities Based on DD Generator Prastowo, Dian Adi
Indonesian Journal of Physics Vol 34 No 2 (2023): vol 34 no 2 2023
Publisher : Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.5614/itb.ijp.2023.34.2.1

Abstract

Design and simulation of radiation facility using deuterium-deuterium (DD) neutron generator for neutron activation analysis (NAA) and radiography have been conducted by PHITS 3.30. A cylindrical DD neutron tube (E = 2.45 MeV isotropic, 5 x 109/s) flux is surrounded by high-density polyethylene blocks which serve as the moderator. Within the moderator there are several cavities to perform neutron activation experiments. A 90 cm long beam tube is installed either radially or tangentially for radiography purposes. Monte Carlo simulations then calculate the thermal flux inside the cavities and on the end of the beam tube. The biggest thermal flux obtained in the activation chambers is about 1.95 x 109/(cm2.s) in the cavity closest to the source center. Radial beam tube delivers thermal flux of 7.86 x 103/(cm2.s), while tangential beam tube transports 1.86 x 103/(cm2.s). Although the thermal flux in the radial beam tube is higher, the fast neutron flux is also higher, about 9.60 x 103/(cm2.s). Tangential beam tube configuration can decrease fast neutron flux to only 2.00 x 102/(cm2.s). This result can serve as a preliminary study for the commisioning of radiation facilities based on compact, low-power neutron source.
Co-Authors Beny Syawaludin Fauzan, Azka Rizqi Fauzi, Amal Hana Subhiyah Isnaini, Ismet Jos Budi Sulistyo Kasmudin Rezon, Kevin Roy Waluyo Sanda Tukiman Yanto, Ausatha Rabbany