ANGULAR NEUTRON FLUX MEASUREMENTS AND NUCLEAR DATA TEST ON SLABS OF FUSION BLANKET MATERIALS


Yukio Oyama, Kazuaki Kosako, Seiya Yamaguchi and Hiroshi Maekawa

Japan Atomic Energy Research Institute
Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan


Angular neutron flux spectra leaking from slab assemblies of Li, Be, C and Li2O with irradiation of DT neutrons have been analyzed to test the nuclear data in JENDL-3T through comparison with the experimental results. The energy spectra were measured in the range of 15 MeV down to 80 keV using the time-of-flight method with an NE213 liquid scintillator. The slab thicknesses were 0.5 to 5 mean free path for 14.8 MeV neutrons. The experiment were analyzed by the Monte Carlo codes, MCNP and MORSE-DD with various nuclear data files. The nuclear data in JENDL-3T show better agreements with the experiments except for beryllium.

KEYWORDS: Angular Neutron Flux, TOF, Fusion Blanket, JENDL-3T, Lithium, Beryllium, Carbon, Lithium- Oxide, MCNP, MORSE-DD