TRU oxide sample reactivity worths measured in the FCA-IX assemblies with systematically changed neutron energy spectra

Abstract

ABSTRACT A series of integral experiments was conducted to evaluate the fission and the capture cross-sections of transuranic (TRU) nuclides at the fast critical facility FCA of the Japan Atomic Energy Agency (JAEA). The experiments were carried out using seven uranium-fueled assemblies of the FCA. The neutron energy spectra of the core regions were adjusted so as to change from an intermediate neutron spectrum to a fast neutron spectrum on an assembly-by-assembly basis. The integral data measured with these experimental configurations provide some neutron energy characteristics: 1) fission rate ratios (FRRs) of 237Np, 238Pu, 242Pu, 241Am, 243Am, and 244Cm relative to 239Pu by using absolutely calibrated fission chambers, 2) small sample reactivity worths (SRWs) of 237Np, 238Pu, 240Pu, 241Am, and 243Am where oxide powders of around 15 to 20 grams were used, 3) criticalities, and 4) spectral indices such as fission rate ratios of 238U relative to 235U. In this paper, details of the SRW measurements are reported, and the latest Japanese Evaluated Nuclear Data Library JENDL-5 is tested by using the integral data obtained in systematically varied neutron energy spectra.