Calculation of absorbed dose and dose distribution in products irradiated in SVST-Co-60/B

  • Trần Văn Hùng
  • Mai Văn Nhơn

Abstract

Code MCNP 4C was used for the calculation of absorbed dose and dose distribution in productions irradiated in Iradiator SVST-Co-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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Published
2017-06-07
Issue
Vol. 9 No. 9 (2006)
Section
ARTILES
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