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Report No.
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The Development for the separation measurement method of Pu-239 and U-235 by using 14 MeV neutron direct interrogation method

Takamine, Jun ; Haruyama, Mitsuo; Takase, Misao; Yamaguchi, Satoshi

We have not yet known the nondestructive detection method to determine each quantity of the object which Uranium and Plutonium is mixed in, such as the waste contaminated by MOX fuel. Then we paid attention to the component of delayed and prompt neutron obtained by 14 MeV neutron direct interrogation method. And from those correlations, we developed the new method to determine the abundance of Uranium and Plutonium. Actually, we made the theory formula of the correlation and perform the experiment where a ratio of Pu-239 and U-235 is the independent variables. As a result, we confirmed that a theory value accorded with experimental value in precision. Furthermore, as a method to drastically reduce a background on measurement of prompt neutron, it has been suggested that graphite reflector was changed in stainless steel. And then, fixed-quantity precision on this technique was also improved greatly by this renovation.

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