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VITJ_FLAT format
The directory FENDLMC/ contains neutron and coupled neutron-photon
pointwise cross section data files in ACE (ASCII) format for use in the Monte-Carlo code
MCNP. Data have been derived from the FENDL/E-2.0 sublibrary using nuclear data processing
code NJOY (output of the module ACER).
Specifications used for processing:
- Temperature: 300 Kelvin = 2.585E-8 eV |
- No thinning |
- Reactions included: |
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- All reactions present in evaluations. |
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- Damage (MT = 444, only for Al-27, Fe-56, Si-28, -29,
-30, Ta-181 and Au-197). |
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- No thermal data. |
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- Gas production data (see below). |
Status of gas production cross sections present in the
FENDL/MC-2.0 sublibrary.
Nuclide |
MT203 |
MT204 |
MT205 |
MT206 |
MT207 |
H-1 |
H-2 |
H-3 |
He-3 |
He-4 |
H-2 |
X |
|
X |
|
|
Be-9 |
|
|
|
|
X |
C-12 |
|
|
|
|
X |
N-14 |
X |
X |
X |
|
X |
O-16 |
X |
X |
|
|
X |
Al-27 |
X |
|
|
|
X |
Si-28 |
X |
X |
|
|
X |
Si-29 |
X |
|
|
|
X |
Si-30 |
X |
|
|
|
X |
V-51 |
X |
X |
X |
|
X |
Fe-56 |
X |
X |
X |
X |
X |
Ga-nat |
X |
X |
X |
X |
X |
Zr-nat |
X |
X |
X |
X |
X |
Nb-93 |
X |
X |
|
|
X |
Mo-nat |
X |
X |
X |
X |
X |
Sn-nat |
X |
X |
X |
X |
X |
Ta-181 |
X |
|
|
|
X |
W-nat |
X |
X |
|
|
X |
Au-197 |
X |
|
|
|
X |
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