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Neutron shielding design for 241Am–Be neutron source considering different sites to achieve maximum thermal and fast neutron flux using MCNPX code

✍ Scribed by Nasrabadi, M.N.; Baghban, G.


Book ID
120270726
Publisher
Elsevier Science
Year
2013
Tongue
English
Weight
868 KB
Volume
59
Category
Article
ISSN
0306-4549

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