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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.

G. Birkhoff, L. Bondár, J. Ley

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Abstract

iiülli ' document was prepared under the sponsorship of the C ommission European C ommunities.Neither the C ommission of the European C ommunities, its contractors "or a" y person acting "" their oenalr : Ì|«MlHfe ike any warranty or representation,

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iiülli ' document was prepared under the sponsorship of the C ommission European C ommunities.Neither the C ommission of the European C ommunities, its contractors "or a" y person acting "" their oenalr : Ì|«MlHfe ike any warranty or representation,

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Available abstract

iiülli ' document was prepared under the sponsorship of the C ommission European C ommunities.Neither the C ommission of the European C ommunities, its contractors "or a" y person acting "" their oenalr : Ì|«MlHfe ike any warranty or representation,

Key concepts: Fissile material, Plutonium-239, Radiochemistry, Uranium-235, Plutonium, Neutron, Nuclear engineering, Nuclear physics

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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. — Research Paper | ScholarLens