The JENDL (alpha,n) Reaction Data File 2005

JENDL (alpha,n) Reaction Data File 2005 (JENDL/AN-2005) contains neutron production cross sections of 17 nuclides for alpha-particle induced reactions.

MAT   Isotope
001   3-LI-  6 
002   3-LI-  7 
003   4-BE-  9 
004   5-B - 10 
005   5-B - 11 
006   6-C - 12 
007   6-C - 13 
008   7-N - 14 
009   7-N - 15 
010   8-O - 17 
011   8-O - 18 
012   9-F - 19 
013  11-NA- 23 
014  13-AL- 27 
015  14-SI- 28 
016  14-SI- 29 
017  14-SI- 30 

The complete set of data evaluations is available for download:

• JENDL-AN-2005.OUT: The ENDF-6 formatted library (1.6 Mb)

• JENDL-AN-2005.CHK: CHECKR output
• JENDL-AN-2005.FIZ: FIZCON output
• JENDL-AN-2005.PSY: PSYCHE output

Last updated: 7 October 2008.