neutron transporting in Gd

Dear all,

1.
While in fluka manual,
"Table 10.3: Materials for which cross-sections are available in the
Fluka neutron library" says:

Material K Origin RN Identifiers gamma

Gd Natural Gadolinium(1) 293 ENDF/B-VI Yes GADOLINI 64 -293 No
Gd Natural Gadolinium(1) 87 ENDF/B-VI Yes available on request

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As i know,
157Gd + n -- 158Gd + gammas + conversio<kman e-+ X-rays
155Gd + n -- 156Gd + gmass + conversion e-+ X-rays
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When neutron transporting in "Gd",is the reactions of the above been
considered in fluka simulation?

As a reference,my recent work is about "developing OSL detectors for
neutron measurements by introducing neutron converters
into the Al2O3:C OSL dosimeters". I don't know if fluka can be capable
to simulate it(from neutron to photon).

2.
Can i simulate neutron transporting in "Yb",while "Yb" isn't in the
Table 1 0.3?

Best regard!
Bob
Received on Wed Aug 03 2011 - 09:55:10 CEST