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Abstract

Code MCNP 4C was used for the calculation of absorbed dose and dose distribution in productions irradiated in Iradiator SVST-C0-60/B in Ho Chi Minh City. The calculation configuration is similar with real one. The obtained calculated results showed that the use of MCNP code for the calculation of the dose distribution, average absorbed dose rate and overdose ratio inside box irradiated in SVST-CO-60/B Irradiator with different product densities is successful. The calculated values agree well with experimental ones.

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Issue: Vol 9 No 9 (2006)
Page No.: 49-54
Published: Sep 30, 2006
Section: Article
DOI: https://doi.org/10.32508/stdj.v9i9.3091

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Copyright: The Authors. This is an open access article distributed under the terms of the Creative Commons Attribution License CC-BY 4.0., which permits unrestricted use, distribution, and reproduction in any medium, provided the original author and source are credited.

 How to Cite
Hung, T., & Van Nhon, M. (2006). CALCULATION OF ABSORBED DOSE AND DOSE DISTRIBUTION IN PRODUCTS IRRADIATED IN SVST-CO-60/B. Science and Technology Development Journal, 9(9), 49-54. https://doi.org/https://doi.org/10.32508/stdj.v9i9.3091


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