Benchmark verifications on neutron reaction nuclear data for nuclear fusion materials. Sr, Cr, Mn, and Cu

Nuclear design of nuclear power plant such as nuclear fusion reactor is carried out by using neutron transport calculation code and diffusion code. If a large error due to the calculation, it is necessary to contain more margin for design parameter, to give a direct effect to construction budget of a plant. Cause of calculation error consists mainly in modelization of geometrical shape and using neutron reaction nuclear data. Adaptability of the nuclear data must be secured by benchmark. Up to date, as an aim of benchmark in recent nuclear data on nuclear fusion materials, leaked neutron spectra from spherical sample pile by time of flight testing method using liquid scintillation counter at the powerful neutron generator at the Engineering Faculty of Osaka University, OKTAVIAN, have been measured. And, as experimental analysis using the MCNP4A Monte Carlo neutron transport calculation code was carried out, a study on effect of partial cross section value on total spectra is now carried out by using sensitivity analytical method, among which four nuclides of Si, Cr, Mn and Cu were reported on their detailed results. (G.K.)