Gamma irradiator dose mapping simulation using the MCNP code and benchmarking with dosimetry-Reference-Cited by-同舟云学术

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

Published:2002-10 Issue:4 Volume:57 Page:537-542
ISSN:0969-8043
Container-title:Applied Radiation and Isotopes
language:en
Short-container-title:Applied Radiation and Isotopes

Author:

Sohrabpour M.,Hassanzadeh M.,Shahriari M.,Sharifzadeh M.

Publisher

Elsevier BV

Subject

Radiation

Reference11 articles.

1. Briesmeister, J.F., 1993. MCNP: a general Monte Carlo N-particle transport code, Version 4A. Los Alamos National Laboratory Report LA-12625.

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3. Kovacs, A., Stenger, V., Foldiak, G., Legeza, I., 1985. Evaluation of irradiated ethanol-mono-chlorobenzene by conductivity method. Proceedings of the Symposium High Dose Dosimetry, IAEA, Vienna, STI/PVB/671, pp. 135–142.

4. MDS Nordion, 1983. IR-136 project proposal, private communication.

5. Dose determination by Monte Carlo, a useful tool in gamma radiation process;Oliveira;Phys. Chem.,2000

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