3. DESCRIPTION OF PROGRAM OR FUNCTION
MATJEF22.BOLIB /1/ is a multigroup coupled (199 neutron groups + 42 photon groups) pseudo-problem-independent cross section library in MATXS format for nuclear fission applications. MATJEF22.BOLIB is based on the JEF-2.2 /2/ European nuclear data file and it was processed, through the NJOY /3/ system, in the VITAMIN-B6 /4/ group structure using the same parameters and calculation procedures.
ORIGINAL NUCLEAR DATA FILE: JEF-2.2
DATA PROCESSING SYSTEMS: NJOY-94.66
FORMAT: MATXS
NUMBER OF GROUPS: 199 neutron groups and 42 photon groups
THERMAL NEUTRON GROUPS: 36 groups below 5.043 eV with upscatter cross sections
NEUTRON ENERGY RANGE: 1.0E-5 eV - 19.64 MeV
PHOTON ENERGY RANGE: 1.0 keV - 30.0 MeV
TEMPERATURES [K]: 300, 600, 1000, and 2100 (same values as in VITAMIN-B6)
BACKGROUND CROSS SECTIONS (SIGMA-ZEROs) [barns]:
1, 10, 50, 100, 300, 1.0E+3, 1.0E+4,
1.0E+5, 1.0E+6, 1.0E+10 (infinite dilution) (same values as in VITAMIN-B6)
LEGENDRE ORDER: P7 for materials with Z < /= 29 (copper); P5 for the remainders
NUMBER OF MATERIALS: 138
MATERIALS INCLUDED: one file per material (nat=natural):
H-H2O H-CH2 H2-D2O H-3 He-3 He-4 Li-6 Li-7
Be-9 Be-TH B-10 B-11 C-nat C-GPH N-14 N-15
O-16 O-17 F-19 Na-23 Mg-nat Al-27 Si-nat P-31
S-32 S-33 S-34 S-36 Cl-nat K-nat Ca-nat Ti-nat
V-nat Cr-50 Cr-52 Cr-53 Cr-54 Mn-55 Fe-54 Fe-56
Fe-57 Fe-58 Co-59 Ni-58 Ni-60 Ni-61 Ni-62 Ni-64
Cu-nat Ga-nat Y-89 Zr-nat Nb-93 Mo-nat Ag-107 Ag-109
Cd-nat Cd-106 Cd-110 Cd-111 Cd-112 Cd-113 Cd-114 Cd-115m
Cd-116 In-113 In-115 Sn-112 Sn-114 Sn-115 Sn-116 Sn-117
Sn-118 Sn-119 Sn-120 Sn-122 Sn-123 Sn-124 Sn-125 Sn-126
Ba-138 Eu-151 Eu-152 Eu-153 Eu-154 Eu-155 Hf-174 Hf-176
Hf-177 Hf-178 Hf-179 Hf-180 Ta-181 Ta-182 W-182 W-183
W-184 W-186 Re-185 Re-187 Au-197 Pb-nat Bi-209 Th-230
Th-232 Pa-231 Pa-233 U-232 U-233 U-234 U-235 U-236
U-237 U-238 Np-237 Np-238 Np-239 Pu-236 Pu-237 Pu-238
Pu-239 Pu-240 Pu-241 Pu-242 Pu-243 Pu-244 Am-241 Am-242
Am-242m Am-243 Cm-241 Cm-242 Cm-243 Cm-244 Cm-245 Cm-246
Cm-247 Cm-248
NEUTRON WEIGHTING SPECTRUM:
Corresponding to the IWT=4 input option in the GROUPR module of NJOY:
from 1.0E-5 eV to 0.125 eV -> Maxwellian thermal spectrum (kT = 0.025 eV)
from 0.125 eV to 820.8 keV -> '1/E' slowing-down spectrum
from 820.8 keV to 19.64 MeV -> fission spectrum (fission temperature = 1.273 MeV)
PHOTON WEIGHTING SPECTRUM:
Corresponding to the IWT=3 input option in the GAMINR module of NJOY:
'1/E' spectrum with a 'roll-off' at lower energies to represent photoelectric absorption and a similar 'drop-off' at higher energies corresponding to the Q-value for neutron capture.
The prompt neutron fission spectra for U-235, U-238 and Pu-239 are included in tabulated form in the package together with the neutron and photon group energy boundaries, the neutron and photon group lethargy boundaries and the neutron and photon group lethargy widths.
The neutron and photon energy weighting spectra in group representation are also included in the package.
Detector response functions are at present not included in the library package.