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

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

Neutron emission data of the reactions were evaluated in the incident -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 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.

Language	:	English
Report No.	:	JAEA-Research 2006-052
Pages	:	63 Pages
Publication Year/Month	:	2006/07
Patent information	:
PDF	:	JAEA-Research-2006-052.pdf:5.11MB
Paper URL	:	https://doi.org/10.11484/jaea-research-2006-052
Keywords	:	no keyword
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Registration No. : RS20060052
JAEA Abstracts No. : 34001065

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