Design calculation of a vertical thermal neutron beam for neutron radiography at Esfahan MNSR
In this paper, the MCNPX code is applied for feasibility study of using the Isfahan MNSR as a neutron source for neutron radiography. To produce a good neutron beam in terms of intensity and quality, the aluminum (Al) with thickness of 0.7 cm, and bismuth (Bi) and lead (Pb) with thickness of 1 cm ar...
| Main Authors: | , , , |
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| Format: | Article |
| Language: | fas |
| Published: |
Nuclear Science and Technology Research Institute
2019-02-01
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| Series: | مجله علوم و فنون هستهای |
| Online Access: | https://jonsat.nstri.ir/article_234_4e34bd77c1240adad30f4d2340c5e195.pdf |