Measurements of Neutron-induced Fission Cross Section of Americium-243 from Thermal Neutron Energy to 15 keV Using Lead Slowing-down Spectrometer and Thermal Neutron Facility

摘要

The neutron-induced fission cross section of 243~Am was measured relative to that of 235~U from thermal neutron energy to 15keV making use of a double fission chamber with 243~Am and 235~U electrodeposited layers. The data above 0.05 eV were measured using a lead slowing-down spectrometer coupled to an electron linear Accelerator. A relative measurement to the 10~B(n,a0 reaction was also made using a BF_3 counter at energies Below 1 keV, and normalized to the absolute value obtained by using the cross section of the 235U(n,f) Reaction between 200 eV and 1 keV.