Abstract
Neutron economy of the transmutation of TRU was examined in well thermalized, thermal and fast neutron fields. Burn-up chains of 237Np, 241Am and 243Am, which are the main TRU nuclides in the high level waste, were calculated in the flux region from 1014 to 1017 n/cm2.s. Numbers of neutrons absorbed and produced of each chain were calculated using JENDL-3. The net number of neutron produced n net, which was obtained by the difference of the two numbers, largely varied with the neutron fields, the nuclides and the flux levels. The n net value in the fast neutron field was positive (0.0–1.0) for 237Np, 241Am, 243Am and TRU with the nuclide composition in the high-level waste generated by the conventional PWR. The transmutation of TRU by fission can be performed with producing neutrons in the fast neutron field. On the other hand, the n net value was negative for the well thermalized and thermal neutron fields. For TRU in the high-level waste, the values in those fields were —1.0 at 1014 n/cm2.s and 0.0 at 1...
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