Gamma irradiator dose mapping simulation using the MCNP code and benchmarking with dosimetry

The Monte Carlo transport code, MCNP, has been applied in simulating dose rate distribution in the IR-136 gamma irradiator system. Isodose curves, cumulative dose values, and system design data such as throughputs, over-dose-ratios, and efficiencies have been simulated as functions of product densit...

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Bibliographic Details
Published in:Applied radiation and isotopes 2002-10, Vol.57 (4), p.537-542
Main Authors: Sohrabpour, M., Hassanzadeh, M., Shahriari, M., Sharifzadeh, M.
Format: Article
Language:English
Subjects:
Benchmarking
Dose mapping
Dosimetry
IR-136 gamma irradiator
MCNP code
Monte Carlo
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Summary:The Monte Carlo transport code, MCNP, has been applied in simulating dose rate distribution in the IR-136 gamma irradiator system. Isodose curves, cumulative dose values, and system design data such as throughputs, over-dose-ratios, and efficiencies have been simulated as functions of product density. Simulated isodose curves, and cumulative dose values were compared with dosimetry values obtained using polymethyle-methacrylate, Fricke, ethanol-chlorobenzene, and potassium dichromate dosimeters. The produced system design data were also found to agree quite favorably with those of the system manufacturer's data. MCNP has thus been found to be an effective transport code for handling of various dose mapping excercises for gamma irradiators.
ISSN:0969-8043
1872-9800
DOI:10.1016/S0969-8043(02)00130-6