Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan
2009 Fall Meeting
Session ID : I01
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Development of a Separation Measurement Method of U-235 and Pu-239 by Using 14 MeV Neutron Direct Interrogation Method, ( II )
*jun takamine, misao takase, mitsuo haruyama
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Keywords: radioactive waste, 14MeV neutron, delayed neutron, prompt neutron, MOX fuel, separation measurement method, active neutron method, fissile
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[in Japanese]
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© 2009 Atomic Energy Society of Japan
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