Monte Carlo simulations and dosimetric studies of an irradiation facility

被引:10
|
作者
Belchior, A. [1 ]
Botelho, M. L. [1 ]
Vaz, P. [1 ]
机构
[1] Inst Tecnol & Nucl, P-2686 Sacavem, Portugal
关键词
cobalt 60 gamma irradiator; MCNPX code; dose mapping; Fricke solution;
D O I
10.1016/j.nima.2007.05.040
中图分类号
TH7 [仪器、仪表];
学科分类号
0804 ; 080401 ; 081102 ;
摘要
There is an increasing utilization of ionizing radiation for industrial applications. Additionally, the radiation technology offers a variety of advantages in areas, such as sterilization and food preservation. For these applications, dosimetric tests are of crucial importance in order to assess the dose distribution throughout the sample being irradiated. The use of Monte Carlo methods and computational tools in support of the assessment of the dose distributions in irradiation facilities can prove to be economically effective, representing savings in the utilization of dosemeters, among other benefits. One of the purposes of this study is the development of a Monte Carlo simulation, using a state-of-the-art computational tool-MCNPX-in order to determine the dose distribution inside an irradiation facility of Cobalt 60. This irradiation facility is currently in operation at the ITN campus and will feature an automation and robotics component, which will allow its remote utilization by an external user, under REEQ/996/BIO/2005 project. The detailed geometrical description of the irradiation facility has been implemented in MCNPX, which features an accurate and full simulation of the electron-photon processes involved. The validation of the simulation results obtained was performed by chemical dosimetry methods, namely a Fricke solution. The Fricke dosimeter is a standard dosimeter and is widely used in radiation processing for calibration purposes. (C) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:70 / 72
页数:3
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