Measurement and analysis of capture reaction rate of Np-237 in various thermal neutron fields by critical assembly and heavy water thermal neutron facility of Kyoto University

Capture reaction rate ratios of Np-237 relative to Au-197 were measured in II thermal neutron fields provided by the Kyoto University Critical Assembl y and the Kyoto University Reactor Heavy Water Neutron Irradiation Facility . In the measurement, both samples of Np-237 and Au-197 were irradiated at the same time, and their gamma activities were measured. The typical experi mental error was 3.5%. The analysis was performed by three steps: full-core calculation, self-shielding correction of the sample, and perturbation cor rection of the sample. Three full-core calculations by a continuous-energy Monte Carlo code (MVP), a transport code (TWOTRAN), and a diffusion code (C ITATION) were made with the JENDL-3.2 library. The self-shielding factors w ere derived by an analytical formula, and the perturbation factors were cal culated by another MVP calculation. The reaction rates were derived by mult iplying the neutron spectrum the two correction factors, and the capture cr oss sections of Np-237 and Au-197. As a result, the three full-core calculations provided almost the same neut ron spectra at the sample position and gave almost the same calculated-to-e xperimental values (C/Es)for the capture reaction rate ratios of Np-237 rel ative to Au-197. Based on the capture cross section of Np-237 taken from th e JENDL-3.2 library, the C/Es were between 0.97 and 1.04, and the average C /E among the II cores was 1.01. On the other hand, the C/Es using the ENDF/ B-VI and the JEF-2.2 were 1.02 to 1.06 for harder spectrum cores, whereas t he C/Es for the softer spectrum cores were 1.08 to 1.16 It is concluded tha t the JENDL-3.2 library has good accuracy for the capture cross section of Np-237 but the ENDF/B-VI and the JEF-2.2 libraries overestimate that of Np- 237 >10% in the thermal neutron energy region.