FENDL/DS-2.0 DOSIMETRY SUBLIBRARY
(POINTWISE)
The data in the file [.FENDLDS]IRDF90V2_XSECT.DAT were obtained by
processing IRDF-90 pointwise data into SAND-II 640 multigroup structure.
It was demonstrated by H.Wienke [INDC(NDS)-337, July 1995] that errors
may be introduced when such multigroup cross sections are re-grouped into
another multigroup structure. Therefore, original pointwise IRDF-90 cross
sections for the following 50 reactions are made available in the
current subdirectory POINTWISE/:
Nuclide: IRDF: Reactions and*) Filename:
uncertainties:
3-Li-6 325 3 105; 33 105 LI6NT.DAT
5-B-10 525 3 1 B10NTOT_NA.DAT
3 107; 33 107
9-F-19 925 3 16; 33 16 F19N2N.DAT
11-Na-23 1123 3 102; 33 102 NA23NG.DAT
12-Mg-24 1225 3 103; 33 103 MG24NP.DAT
13-Al-27 1325 3 103; 33 103 AL27NP.DAT
3 107; 33 107 AL27NA.DAT
15-P-31 1525 3 103; 33 103 P31NP.DAT
16-S-32 1625 3 103; 33 103 S32NP.DAT
21-Sc-45 2126 3 102; 33 102 SC45NG.DAT
22-Ti-46 2225 3 103; 33 103 TI46NP.DAT
22-Ti-47 2228 3 28; 33 28 TI47NNP.DAT
3 103; 33 103 TI47NP.DAT
22-Ti-48 2231 3 28; 33 28 TI48NNP.DAT
3 103; 33 103 TI48NP.DAT
24-Cr-52 2431 3 16; 33 16 CR52N2N.DAT
25-Mn-55 2525 3 16; 33 16 MN55N2N_NG.DAT-GZ;1
3 102; 33 102
26-Fe-56 2631 3 103; 33 103 FE56NP.DAT
26-Fe-58 2637 3 102; 33 102 FE58NG.DAT
27-Co-59 2725 3 16; 33 16 CO59N2N.DAT
3 107; 33 107 CO59NA.DAT
28-Ni-58 2825 3 103; 33 103 NI58NP.DAT
3 16; 33 16 NI58N2N.DAT
28-Ni-60 2831 3 103; 33 103 NI60NP.DAT
29-Cu-63 2925 3 16; 33 16 CU63N2N.DAT
3 102; 33 102 CU63NG.DAT-GZ
3 107; 33 107 CU63NA.DAT
29-Cu-65 2931 3 16; 33 16 CU65N2N.DAT
30-Zn-64 3025 3 103; 33 103 ZN64NP.DAT
39-Y-89 3925 3 16; 33 16 Y89N2N.DAT
40-Zr-90 4025 3 16; 33 16 ZR90N2N.DAT
41-Nb-93 4125 3 16; 33 16 NB93N2N_NINL1.DAT
3 51; 33 51
3 102; 33 102 NB93NG.DAT-GZ
45-Rh-103 4525 3 51; 33 51 RH103NINL1.DAT
47-Ag-109 4731 3 102; 33 102 AG109NG.DAT
48-Cd-0 4800 3 1 CDNATNG_NTOT.DAT
3 102
49-In-115 4931 3 16; 33 16 IN115N2N.DAT
53-I-127 5325 3 16; 33 16 I127N2N.DAT
79-Au-197 7925 3 102; 33 102 AU197NG.DAT-GZ
3 16; 33 16 AU197N2N.DAT
90-Th-232 9040 3 18; 33 18 TH232NF_NG.DAT-GZ
3 102; 33 102
92-U-235 9228 3 18; 33 18 U235NF.DAT-GZ
92-U-238 9237 3 18; 33 18 U238NF.DAT-GZ
3 102; 33 102 U238NG.DAT-GZ
92-Np-237 9337 3 18; 33 18 NP237NF.dat-GZ
All those files have been concatenated into the file
IRDF-P.DAT-GZ.
The pointwise data for the following reactions in the file
FENDLDS/IRDF90V2_XSECT.DAT are not (yet) available:
Nuclide IRDF Reactions and*)
MAT No. Uncertainties
23-V-0 2300 3 107; 33 107
26-Fe-54 2625 3 103; 33 103
27-Co-59 2725 3 102; 33 102
49-In-115 4931 3 51; 33 51
3 102; 33 102
64-Gd-0 6400 3 1
3 102
94-Pu-239 9437 3 18; 33 18
Note: *) The following ENDF notation is used:
3 = cross-section data file.
33 = covariance data file.
for reactions:
1 = total
16 = (n,2n)
18 = fission
28 = (n,np)
51 = total(!) population of the 1st discrete level (different
from the ENDF definition, includes also contributions from
the gamma cascade)
102 = (n,gamma)
103 = (n,p)
105 = (n,t)
107 = (n,alpha)
page modified: 6.4.1998
![[ICO]](/icons/blank.gif){kind=icon}
![[PARENTDIR]](/icons/back.gif){kind=icon}
![[VID]](/icons/movie.gif){kind=icon}
![[ ]](/icons/unknown.gif){kind=icon}