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Acemap > Paper > Determination of the U 235, Pu 239 and Pu 240 Contents in Mixed Fissile Materials by Means of Active and Passive Neutron Techniques. EUR 4778.

Determination of the U 235, Pu 239 and Pu 240 Contents in Mixed Fissile Materials by Means of Active and Passive Neutron Techniques. EUR 4778.

1972 
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