FENDL/MG-2.0 GENERAL PURPOSE SUBLIBRARY
(FENDL/E-2.0 processed into multigroup structure)
The directory FENDLMG/ contains the
multigroup neutron, photon-atom and coupled neutron-photon cross section
data generated with the nuclear data processing code NJOY94 for neutron-photon
transport calculations.
The multigroup data are available in two formats:
1. GENDF (file ext. .G) - output of the GROUPR module (neutron and coupled
neutron-photon cross section data only).
2. MATXS (file ext. .M) - for use in coupled neutron-photon transport
calculations with discrete-ordinates codes like anisn,
one- and two-dant. These MATXS files were generated by
post-processing the above mentioned GENDF files
with the MATXSR module of NJOY, along with the
GENDF files of photon-atom interaction data. The
latter were generated with the NJOY modules
RECONR/GAMINR from the evaluated photon-atom cross
section data file
[FENDL2.TRANSPORT.FENDLE]FENDLEP.DAT.
Following examples illustrate name convention adopted for the files:
H002BR2.* H -2 data from BROND-2
SI030E6.* Si -30 data from ENDF/B-VI
MO000JFF.* Mo-nat data from JENDL-FF
FE056EFF3.* Fe -56 data from EFF-3
TA181J3.* Ta-181 data from JENDL-3.1
Here, '*' is to be replaced by 'G' for GENDF files and by 'M' for MATXS files.
The atomic number is always represented by three digits, using '0' in front
whenever appropriate.
A file named 'NJOY-INPUT.DAT' contains the NJOY input files for processing
the data into multigroup structure.
ATTENTION: files with -GZ suffix are compressed with GNU gzip
(use gzip -d "file.name" to uncompress downloaded file).
Specifications of the multigroup processing for producing GENDF and
MATXS files:
- Neutron groups: 175, in Vitamin-J structure
- Gamma groups: 42, in Vitamin_J structure
- Vitamin-E neutron weight function (IWT=11 in NJOY)
- Gamma weight function: 1/E with roll-offs (IWT=3 in NJOY)
- Legendre order for neutron and photon scattering: P6 for transport
correction to P5
- Temperature: 300 Kelvin ( plus 600, 900 and 1200 K for Ga-nat
and -JFF data)
- Dilution factors: (see Table 1)
- Reconstruction, linearization and thinning tolerances used in
RECONR: 0.2%
- Up to 7 digits of accuracy for resonance reconstruction.
- Reactions included:
* All reactions present in evaluations
* Energy balance heating (MT = 301)
* Kinematic heating (Mt = 443)
* Damage (MT = 444)
* Thermal data only for H-2, Be-9, C-12, N-14,
O-16, Al-27, V-51, Fe-56, Zr-nat, Ga-nat,
Nb-93, Mo-nat, Sn-nat, W-nat, Au-197
* Gas production data (see Table 2)
Table 1: Status of the multigroup files for different dilution factors
( in barns).
----------------------------------------------------------------------------------------
Nuclide |10**10|10**5|10000| 1000| 300| 100| 30| 10| 3| 1| 0.3| 0.1| .001
----------------------------------------------------------------------------------------
H-1 | X | | | | | | | | | | | |
H-2 | X | | X | X | | X | | X | | X | | |
H-3 | X | | | | | | | | | | | |
He-3 | X | | | | | | | | | | | |
He-4 | X | | | | | | | | | | | |
Li-6 | X | | | | | | | | | | | |
Li-7 | X | | | | | | | | | | | |
Be-9 | X | | X | X | X | X | X | X | | X | | X | X
B-10 | X | | | | | | | | | | | |
B-11 | X | | | | | | | | | | | |
C-12 | X | | X | X | X | X | X | X | | X | | X | X
N-14 | X | | X | X | X | X | X | X | | X | | X | X
N-15 | X | | | | | | | | | | | |
O-16 | X | | X | X | X | X | X | X | | X | | X | X
F-19 | X | | | | | | | | | | | |
Na-23 | X | | | | | | | | | | | |
Mg-Nat | X | | | | | | | | | | | |
Al-27 | X | | | | | | | | | | | |
Si-28 | X | | | | | X | | X | | X | | |
Si-29 | X | | | | | X | | X | | X | | |
Si-30 | X | | | | | X | | X | | X | | |
P-31 | X | | | | | | | | | | | |
S-Nat | X | | | X | X | X | X | X | | | | |
Cl-Nat | X | | | X | X | X | X | X | | | | |
K-Nat | X | | | X | X | X | X | X | | | | |
Ca-Nat | X | | | X | X | X | X | X | X | X | | |
Ti-Nat | X | | | X | X | X | X | X | X | X | | |
V-51 | X | | X | X | X | X | X | X | | X | | X | X
Cr-50 | X | | | X | X | X | X | X | X | X | | |
Cr-52 | X | | | X | X | X | X | X | X | X | | |
Cr-53 | X | | | X | X | X | X | X | X | X | | |
Cr-54 | X | | | X | X | X | X | X | X | X | | |
Mn-55 | X | X | | X | | X | | X | | X | | |
Fe-54 | X | X | X | X | | X | | X | | | | |
Fe-56 | X | X | X | X | | X | | X | X | X | X | X |
Fe-57 | X | X | X | X | | X | | X | | | | |
Fe-58 | X | X | X | X | | X | | X | | | | |
Co-59 | X | X | X | X | | X | | X | | | | |
Ni-58 | X | | | X | X | X | X | X | X | X | | |
Ni-60 | X | | | X | X | X | X | X | X | X | | |
Ni-61 | X | | | X | X | X | X | X | X | X | | |
Ni-62 | X | | | X | X | X | X | X | X | X | | |
Ni-64 | X | | | X | X | X | X | X | X | X | | |
Cu-63 | X | | X | | X | X | X | X | | | | |
Cu-65 | X | | X | | X | X | X | X | | | | |
Ga-nat | X | | X | X | X | X | X | X | | X | | X | X
Zr-nat | X | | X | X | X | X | X | X | | X | | X | X
Nb-93 | X | | X | X | X | X | X | X | | X | | X | X
Mo-Nat | X | | X | X | X | X | X | X | | X | | X | X
Sn-Nat | X | | X | X | | X | | X | | X | | |
Ta-181 | X | | X | X | | X | | X | | | | |
W-nat | X | | X | X | X | X | X | X | | X | | X | X
Au-197 | X | | X | X | X | X | X | X | | X | | |
Pb-206 | X | | | X | | X | | X | | X | | |
Pb-207 | X | | | X | | X | | X | | X | | |
Pb-208 | X | | | X | | X | | X | | X | | |
Bi-209 | X | | X | X | | X | | X | | | | |
-------------------------------------------------------------------------------------
Table 2: Status of gas production cross sections present in
the multigroup libraries.
------------------------------------------------------------
| MT203 | MT204 | MT205 | MT206 | MT207
Nuclide | 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
W-nat | X | X | | | X
Au-197 | X | | | | X
------------------------------------------------------------
page modified: 24.4.1998
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