EVALUATION OF SOME ACTIVATION CROSS SECTIONS MEASURED BY MONOENERGETIC AND FISSION NEUTRONS
Department of Energy Conversion Engineering
Kasuga, Fukuoka 816, Japan
Neutron-induced activation cross sections applied in neutron dosimetry must be evaluated as accurate as possible and also their evaluated covariances are demanded in computer codes to unfold neutron spectra from dosimeter activities. The six activation cross sections, 27Al(n,p), 27Al(n,α), 54Fe(n,p), 56Fe(n,p), 59Co(n,α), and 58Ni(n,p) and their covariances have been simultaneously evaluated from differential experiments in which samples are activated with monoenergetic neutron sources and the integral experiments with 235U(n,f) and 252Cf(spontaneous) fission neutron spectra. The evaluated cross sections are smaller than those only with the differential data.
KEYWORDS: Bayesian Method, Neutron Dosimetry, Fission Neutron Spectra, Sections, Simultaneous Evaluation