Measurement and Analysis of Fission and Capture Fission Cross Section Ratios of 237Np/235U
-
Graphical Abstract
-
Abstract
It is very difficult to measure the fission and capture fission cross sections of 237Np directly in China Experimental Fast Reactor (CEFR) and there are always obvious deviations in the measurement result. Because CEFR uses UO2 as the fuel loading, the related cross section data of 237Np can be obtained through measuring the fission and capture fission cross section ratios of 237Np/235U. By analyzing the result of the cross section ratios, the related cross section data of 237Np were obtained in this paper. It will provide great support for 237Np transmutation and isotope production in CEFR through these data.
-
-