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KMID : 0364920070320010021
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Journal of Radiation Protection and Research
2007 Volume.32 No. 1 p.21 ~ p.26
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Dose Determination in the IR-221 Gamma Facility Using a Monte Carlo Simulation
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Lim Ik-Sung
Kim Ki-Yup
Roh Gyu-Hong
Lee Chung
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Abstract
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This study is performed to evaluate the dose rate and to analyze the dose distribution of the gamma irradiation facility (IR-221) by using a Monte Calro simulation, which is helpful of upgrading the radiation processing qualification. Monte Cairo simulation is performed by MCNP4B code. Dose rates were measured at total 369 points with alanine dosimeters to compare the calculation results and the measurements data. The results have shown that the MCNP4B code is very useful to determine the dose distribution of the IR-221 gamma irradiation facility, as the calculation dose rate is within about ${\pm}5%$ of the measurement data. Dosimetry about the gamma irradiation facility usually needs enormous manpower and time. However Monte Cairo calculation method can reduce the tedious dosimetry jobs and improve the irradiation processing qualification, which will probably contribute to obtain the reliability of the irradiation products.
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KEYWORD
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MCNP4B, IR-221 irradiator, Alanine, Dose uniformity
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