n 1 - IAEA Nuclear Data Services

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Nuclide, Mat. No. 26-Fe-56, 6431
Nuclide, Mat. No.
Energy Range (eV)
Evaluation Lab., Date
Main Reference
Cross Section Standard
Comments
Quantity (Data type)
Notes
Nuclide, Mat. No.
Energy Range (eV)
Evaluation Lab., Date
Main Reference
Cross Section Standard
Comments
This was not included in the original ENDF/B-5
Standards Library but added by the IAEA Nuclear
Data Section as extracted from the ENDF/B-5
Dosimetry Library, version 2 of 1984
79-AU-197, 1379 Mod.3
1.0E-5 - 2.0E+7
BNL, February 1977
S.F. Mughabghab; unpublished
(N,G) cross section from 200 keV to 3.5 MeV
The total, elastic, and gamma production cross
sections in the resonance region are background
files which must be added to the cross section
calculated from the resonance parameters to
give the real cross section
RRP (from 1.0e-5eV to 2 keV), Thermal cross
sections (Capture = 98.71 B, scattering = 6.84
B, total = 105.55 B, absorption resonance
integral = 1559B), Total(I), Elastic(I,A),
Inelastic(I), (N.2N)(I,A,E), (N,3N)(I,A,E),
(N.GXI), (N,P)(I), (N,A)(I)
Minor modifications were made in 1986
: 92-U-235, 1395 Mod. 3
: 1.0E-5 - 2.0E+7
: BNL, April 1977
: M.R. Bhat; BNL-NCS-51184 (March 1980)
: (N,F) cross section at thermal, and from 100
keV to 20 MeV
: The total, elastic, fission, and gamma
production cross sections in the resonance
region are background files which must be added
to the cross section calculated from the
resonance parameters to give the real cross
section