Monte-Carlo Determination of Dose Rates In Spherical Pressurized Water Reactor Shield

Le Van Ngoc; Trinh Dang Ha

doi:10.15625/0868-3166/20/1/2155

Monte-Carlo Determination of Dose Rates In Spherical Pressurized Water Reactor Shield

Le Van Ngoc, Trinh Dang Ha

Author affiliations

Authors

Le Van Ngoc Communications in Physics, VAST
Trinh Dang Ha

DOI:

https://doi.org/10.15625/0868-3166/20/1/2155

Abstract

The nuclear reactor emits various kinds of nuclear radiations during operation. However, the main contributions to the radiation field in the reactor are given by neutrons and gamma rays. These radiation components are the principal concern of reactor shielding. In our study the neutron and gamma radiation dose rates at different depths in concrete bio-shield of the PWR were calculated based on spherical model for M-C simulation with using MCNP4C2. The simulation results were compared with the results obtained from calculations based on S$_{8}$P$_{3}$ spherical approximation with using the ANISN code.

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Published

15-03-2010

How to Cite

[1]

L. V. Ngoc and T. D. Ha, “Monte-Carlo Determination of Dose Rates In Spherical Pressurized Water Reactor Shield”, Comm. Phys., vol. 20, no. 1, p. 91, Mar. 2010.

IEEE

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Issue

Vol. 20 No. 1 (2010)

Section

Papers

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