Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1728160 | Annals of Nuclear Energy | 2014 | 5 Pages |
Abstract
•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.
Keywords
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
S. Al-Ayoubi, I. Sulieman,