Styudy of precise measurement of neutron capture cross section for radioactive nuclear wastes

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The neutron capture cross-section was measured by an activation method at Kyoto Reactor Research Institute. A Gd foil was used to set Cut-off energy as 0.13eV to pay attention in the 0.489-eV resonance of Np-237. The amount for Np-237 and Np-238 were measured from measurements of gamma-rays emitted from Pa-233 and Np-238. The neutron fluxes were monitored with Co/Al and Co/Al alloy wires. The thermal-neutron capture cross-section of Np-237 was derived from the production amount of Np-238 and neutron fluxes, and obtained as 198+-10(b). It was found that this result was about 10% larger than the evaluated value (178.1(b)).