Feasibility analysis for the construction of vertical neutron beam in the MNSR

• The MCNP-4C code is used to model the MNSR reactor.
• The possibility of extracting a neutron beam from the MNSR reactor is investigated.
• The proposed guide is to be constructed in the water pool adjacent to the vessel.
• The vertical guide tube inlet is located in level with the reactor core centre.
• Vertical beam with thermal neutron flux of about (6 × 105) cm−2 s−1 could be obtained.

The MCNP-4C code has been used to investigate the possibility of extracting a vertical neutron beam from the MNSR reactor. Code results showed that a beam with thermal neutron flux at the exit aperture of about (6 × 105) cm−2 s−1 could be obtained and neutron beam properties were determined.