Hi Xu Lijun,
ENDF/B-VI is just a generic name for several versions, the latest being
ENDF/B-VI.8 (or ENDF/B6R8). Which version are you talking about?
Versions older than 8 are non available anymore on NNDC and the IAEA websites,
so I cannot check if there are differences. But anyway the carbon and oxygen
cross sections in FLUKA have been taken from ENDF/B-VI.8 since at least 2003,
and those of carbon are presently from ENDF/B-VII.0.
Looking at the recent versions (not only ENDF/B-VI.8 but also ENDF/B-VII.0
and ENDF/B-VII.1) it appears that it is not true what you say, that "The
interaction between low energy neutron and oxygen or carbon material is
mainly elastic scattering, so there couldn't be a peak in the pulse height
spectrum". The total cross section shows large peaks due to inelastic reactions
above 0.5 MeV, for both carbon and oxygen.
Alberto
On Tue, 10 Jan 2012, Xu Lijun wrote:
> Dear FLUKA experts,
> I really want to know which cross-sections in the FLUKA neutron
> library. I found that the cross-sections origin for materials oxygen and
> carbon is ENDF/B6R8. Is it very different from ENDF/B-VI?
> Here is my problem. When I simulated the low energy neutron
> interaction with oxygen or carbon material, there was a mono-energy peak
> in the pulse height spectrum. But according to the cross-section data
> from ENDF/B-VI, the pulse height spectrum should be smooth and the
> mono-energy peak couldn't appear. The interaction between low energy
> neutron and oxygen or carbon material is mainly elastic scattering, so
> there couldn't be a peak in the pulse height spectrum.
> Best regards,
Received on Wed Jan 11 2012 - 11:10:10 CET
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