Determination of Neutron Flux Distribution along the Dry-Channel of the MNSR Reactor and Determination of Neutron Energy Spectrum in this Reactor
In this work, the relative neutron flux was determined experimentally using neutron activation analysis (NAA) method along the length of the dry channel (GUIDE TUBE) of the Isfahan miniature neutron source reactor (MNSR). This reactor was also simulated using the MCNP code, and the neutron flux dist...
| Main Authors: | , , |
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| Format: | Article |
| Language: | fas |
| Published: |
Nuclear Science and Technology Research Institute
2011-05-01
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| Series: | مجله علوم و فنون هستهای |
| Subjects: | |
| Online Access: | https://jonsat.nstri.ir/article_428_d868fc8dd23699f848ebc8ba54550717.pdf |