EVALUATION AND ADJUSTMENT OF ACTINIDE CROSS SECTIONS USING INTEGRAL DATA MEASURED AT FCA
Japan Atomic Energy Research Institute
Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan
The actinide integral experiments were conducted in the IX series assemblies (standard neutron spectrum assemblies) of FCA. The 20 group fission and capture cross sections of actinide nuclides processed from JENDL-2 library were evaluated and adjusted using these integral data. These adjusted cross sections were checked using the integral data measured in the assemblies other than the IX series. It is concluded that the adjusted cross sections can be generally used in fast spectrum.
KEYWORDS: actinide cross sections, cross section evaluation and adjustment, integral experiment, least squares fitting, fast reactor, fission rate ratio, sample reactivity worth, neutron spectrum, higher actinide, fast critical facility