Fission Product Yields of 233U, 235U, 238U and 239PU in Fields of Thermal Neutrons, Fission Neutrons and 14.7-MeV Neutrons

techniques, for U-235(n,f), Pu-239(n,f) in a thermal spectrum, for U-233(n,f), U-235(n,f), and Pu-239(n,f) reactions in a fission neutron spectrum, and for U-233(n,f), U-235(n,f), U-238(n,f), and Pu-239(n,f) for 14.7 MeV monoenergetic neutrons. Irradiations were performed at the EL3 reactor, at the Caliban and Prospero critical assemblies, and at the Lancelot electrostatic accelerator in CEA-Valduc. Fissions were counted in thin deposits using fission ionization chambers. The number of fission products of each species were measured by gamma spectrometry of co-located thick deposits.