International Reactor Dosimetry File 2002 - IAEA Publications

(b)
(c)
Pointwise data:
(i) All dosimetry cross-sections listed above, accompanied by
uncertainty information except for radiation damage cross-sections;
(ii) Total cross-sections of all of the target nuclides present in the library.
Nuclear data:
(i) Decay data for all reaction product nuclei of interest;
(ii) Isotopic abundances for all target nuclei of interest.
Pointwise cross-section data are given in the ENDF-6 format, while
multigroup data are supplied as SAND II 640 energy group structure
(simplified form of ENDF-6). The neutron temperature in both cases is 300 K.
However, multigroup cross-section data were also generated for a neutron
temperature of 0 K, and compared with the corresponding values obtained at
300 K; the differences between these two files were in most cases smaller than
1% and within the uncertainties of the data treatment. The multigroup crosssection
data are fully characterized within this report, and all of the results
presented in the various sections are based on this form of the IRDF-2002
library.
Table 1.1 lists the reactions contained in IRDF-2002, together with the
origin of the corresponding cross-section data. The selection procedure applied
to the cross-sections for inclusion in the library is described in Sections 3–6. The
corresponding integral data for the cross-sections present in the file (e.g. crosssections
at 2200 m/s, the resonance integrals and the 252 Cf fission spectrum
averaged cross-sections) are given in Table 6.2 in Section 6.
TABLE 1.1. CONTENTS OF IRDF-2002, AND SOURCES OF THE DATA
Reaction Selected source Reaction Selected source
6 Li(n,t) 4 He IRDF-90 a 65 Cu(n,2n) 64 Cu IRDF-90 a
10 B(n,α) 7 Li IRDF-90 64 Zn(n,p) 64 Cu IRDF-90
19 F(n,2n) 18 F RRDF-98 (u) 75 As(n,2n) 74 As RRDF-98 (u)
23 Na(n,γ) 24 Na b IRDF-90 a 89 Y(n,2n) 88 Y JENDL/D-99
23 Na(n,2n) 22 Na JENDL/D-99 (u) 90 Zr(n,2n) 89 Zr IRDF-90
24 Mg(n,p) 24 Na IRDF-90 93 Nb(n,2n) 92 Nb m RRDF-98
27 Al(n,p) 27 Mg RRDF-98 (n) 93 Nb(n,n′) 93 Nb m RRDF-98
27 Al(n,α) 24 Na IRDF-90 93 Nb(n,γ) 94 Nb b IRDF-90 a
31 P(n,p) 31 Si IRDF-90 103 Rh(n,n′) 103 Rh m RRDF-98 (n)
32 S(n,p) 32 P IRDF-90 109 Ag(n,γ) 110 Ag m IRDF-90
45 Sc(n,γ) 46 Sc IRDF-90 115 In(n,2n) 114 In m IRDF-90 a
3