APLIKASI PENSILBARIS1.2 UNTUK DESAIN KESELAMATAN IRADIATOR GAMMA BATAN 500K
Keywords:
gamma irradiators, radiation dose rate, total radiation dose, radiation safety, radiation shielding, PensilBaris, MCNP5Abstract
The safety aspects of the gamma radiation application, especially in using of gamma irradiators is required to guarantee the personnel safety and environmental safety. The radiation safety of workers is reckoned in normal operation of the irradiation facility and in loadingunloading of radiation source and maintenance or repairing of this facility when radiation source inside the storage pool or in the depository racks. The type and thickness of concrete wall that serves as radiation shielding should be considered, so the radiation exposure in the environment fulfil with the radiation safety criteria established by BAPETEN. Calculation performed by using the PensilBaris1.2 computer code with a point kernel integration technique and as comparison using MCNP5 code with the Monte Carlo techniques. The facility of innovative gamma irradiator has dimension of length, wide dan hight 13, 6 and 4 m, respectively and gamma sources emitted from 36-52 Cobalt-60 rods with 500 kCi total activities that are arranged in a pair of parallel 2-level rack in 135 cm long and 100 cm height. The results of calculation using PensilBaris1.2 give a thickness of 2.45 g/cm3 density concrete wall in length, wide and hight are 14.,6; 164.4 and 15.,6 cm, revectively. Similar analysis using MCNP5 but for 2.45 g/cm3 density concrete wall, giving the thickness of 145, 155 and 140 cm, resvectively. The difference results from both tools, other than due to the technical and computational methods are different, may be caused also by differences in the data library of the photon interaction cross-section to the matter and dose built-up factor used. Meanwhile, the result from PensilBaris1.2 using density of concrete wall 2.35 g/cm3 give the thickness of wall in length, wide and hight of 147.4; 170.7 and 161.4 cm, respectively. Minimum under water depth of the upper end of the source rack from the water surface using PensilBaris1.2 giving 4.85 m for 0.25 mrem/h and 3.25 m for the limit value 2.5 mrem/h dose rate, whereas using MCNP5 giving not so much significantly different values. Based on these calculations the basic design of gamma irradiator facility has been made and then it will be continued to detail design so after that it can be fabricated for operation.
References
John R. Lamarsh. Introduction to Nuclear Engineering. 2nd Ed. Addison-Wesley Publishing Company, Reading, Massachusetts; 1983.
James Wood Computational methods in reactor shielding. Pergamon Press., Headington Hill Hall, Oxford OX3 OBW, England; 1982.
Pudjijanto MS et all. Rancangbangun detil dan analisis laju dosis radiasi iradiator gamma sebagai pengawet bahan pangan/hasil pertanian, tahap II. Laporan Teknis PRPN-BATAN No. BATAN-RPN-L-2010-06-046; 2010.
Wilson A. P. Calvo, et all. A small size continuous run industrial gamma irradiator. ELSEVIER, Radiation Physics and Chemistry. 2004; 71: 561-563.
https://doi.org/10.1016/j.radphyschem.2004.03.027
Nelson M. Omi, Paulo R. Rela. Gemstone dedicated gamma irradiator development. 2007 International Nuclear Atlantic Conference - INAC 2007, Santos, SP, Brazil; September 30 to October 5, 2007.
Pudjijanto MS. PensilBaris Ver-1.2 - Program PC dalam Fortran-77 untuk perhitungan laju dosis radiasi dan prakiraan tebal dinding dan atap instalasi fasilitas iradiator- dan kedalaman benam sumber dalam kolam penyimpan sumber. 2525 rekord, 111 kb, runable, belum dipublikasi; 2010.
Setiyanto, Pudjijanto MS. Ardani. Analisis laju dosis iradiator gamma menggunakan elemen bakar bekas dengan model konfigurasi sejajar. Tri Dasa Mega. Jurnal Teknologi Reaktor Nuklir. 2006; 8: 148 - 160
Monte Carlo Team. MCNP-A general Monte Carlo neutral-particle transport code. Version 5, X-5, Los Alamos National Laboratory; 2003.
Rogério R. RODRIGUES, at all. Gamma irradiator dose mapping: A Monte Carlo simulation and experimental measurements. 2009 International Nuclear Atlantic Conference - INAC 2009, Rio de Janeiro,RJ, Brazil, September27 to October 2, 2009. Associação Brasileira De Energia Nuclear - ABEN, ISBN: 978-85-99141-03-8, http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/41/115/411157 58. pdf. Accessed January 2010.
Ka Bapeten. Surat Keputusan Kepala Badan Pengawas Tenaga Nuklir Republik Indonesia No. 11/Ka-Bapeten/VI-99, Tgl. 15 Juni 1999, tentang Izin Konstruksi dan Operasi Iradiator; 1999.
MDS Nordion. Sciences advencing health. The Standard. C-188 Cobalt-60, 447 March Road, Ottawa, ON K2IK 1X8, Kanada. Available from URL http://www. mds.nordion.com documents/products/C-188_Brochure.pdf. Accessed, July 2010.
J. Kenneth Shultis , Richard E. Faw. Shldutil : A Code for useful shielding data. dept. of mechanical and nuclear engineering. Kansas State University, Manhattan, KS 66506; Available from URL: http://http:// ww2.mne.ksu.edu/~jks/ pgms.htm. Accessed, October 2009.
Kishor Mehta, Andrzej G. Chmielewski. Gamma irradiators for radiation processing. IAEA's Industrial Applications and Chemistry Section, Division of Physical and Chemical Sciences , 44 hlm., IAEA, WINA; Available from URL:: http://www-naweb.iaea.org/napc/iachem/Brochgammairradd.pdf. Accessed, October 2009.
J. Masefield , et all. Guidelines for industrial radiation sterilization of disposable medical products (Cobalt-60 Gamma Irradiation). IAEA-TECDOC-539, IAEA, Wina, 1990; Available from URL: http://www-pub.iaea.org/ MTCD/ publications/PDF/te_539_web.pdf. Accessed June 2010.
