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Report No.

Evaluation of the ($$alpha$$,xn) reaction data for JENDL/AN-2005

Murata, Toru*; Matsunobu, Hiroyuki*; Shibata, Keiichi

Neutron emission data of the $$(alpha,xn)$$ reactions were evaluated in the incident $$alpha$$-particle energy region below 15 MeV for nuclides important mainly in nuclear fuel-cycle applications, namely, $$^{6,7}Li$$, $$^{9}Be$$, $$^{10,11}B$$, $$^{12,13}C$$, $$^{14,15}N$$, $$^{17,18}O$$, $$^{19}F$$, $$^{23}Na$$, $$^{27}Al$$ and $$^{28,29,30}Si$$. The evaluation was performed on the basis of available experimental data and nuclear model calculations. The evaluated nuclear data were compiled in the ENDF-6 format, and released in June 2005 as JENDL $$(alpha,n)$$ Reaction Data File 2005 (JENDL/AN-2005) which is one of JENDL special-purpose files. This report describes evaluation methods and the results on evalauted cross sections and angular- and energy-distributions of emitted neutrons.



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