Computing the Neutron Flux in VVRS-2 Reactor using MCNP-4C

M  Rahgoshay; M  Khaleghi   and M  Hashemi Tilehnoee

doi:10.17485/ijst/2015/v8i12/56479

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Computing the Neutron Flux in VVRS-2 Reactor using MCNP-4C

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Indian Journal of Science and Technology

DOI: 10.17485/ijst/2015/v8i12/56479

Year: 2015, Volume: 8, Issue: 12, Pages: 1-5

Original Article

Computing the Neutron Flux in VVRS-2 Reactor using MCNP-4C

M. Rahgoshay^1*, M. Khaleghi ² and M. Hashemi-Tilehnoee³

¹Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran; [email protected]

²Department of Mechanical Engineering, Sirjan University of Technology, Kerman, Iran

³Young Researchers and Elite Club, Aliabad Katoul Branch, Islamic Azad University, Aliabad Katoul, Iran

This work is licensed under a Creative Commons Attribution 4.0 International License.

Abstract

The MCNP-4C Monte Carlo code was used to model a 2 MW thermal VVR-S research reactor. The neutron with continuous energy cross sections of the ENDF/B-VI library was applied to MCNP-4C to calculate the thermal and fast neutron fluxes. The computed neutron flux showed that the MCNP-4C can be used in the reactors similar to VVR-S reactor.

Keywords: MCNP, Multiplication Factor, Neutron Flux, VVR-S