International Reactor Dosimetry File 2002 - IAEA Publications

TABLE 6.2. CROSS-SECTIONS IN IRDF-2002 AND THEIR CHARACTERISTICS (TEMPERATURE OF 300 K) (cont.)
Reaction
Selected
evaluation
Calculated
library crosssection
(2200 m/s)
σ L (b)
Resonance
integral from
library data
IR L (b)
Uncertainty in
library data
Thermal
(%)
Epithermal
(%)
Calculated average
library crosssection
in 252 Uncertainty in
Cf
(%) a C/E
fission (mb) a
63 Cu(n,2n) ENDF/B-VI — — — — 0.2056 4.10 (5.81) 1.115 ± 0.078
a
63 Cu(n,γ) IRDF-90 4.47 4.96 4.11 3.86 — — Thermal: 0.99 ± 0.04
d
0.99 ± 0.06 b
Epithermal: 1.00 ± 0.04, d
0.99 ± 0.04 b
63 Cu(n,α) RRDF-98 (u) — — — — 0.6933 2.83 (3.15) 1.007 ± 0.037
a
65 Cu(n,2n) IRDF-90 — — — — 0.6779 1.83 (3.44) 1.030 ± 0.042
a
64 Zn(n,p) IRDF-90 — — — — 42.10 4.87 (4.93) 1.037 ± 0.054
a
75 As(n,2n) RRDF-98 (u) — — — — 0.6209 5.76 (6.55) No experimental data in
252 Cf fission field
89 Y(n,2n) JENDL/D-99 — — — — 0.344 1.40 (4.47) No experimental data in
252 Cf fission field
90 Zr(n,2n) IRDF-90 — — — — 0.2212 1.57 (5.31) 1.001 ± 0.061
a
93 Nb(n,2n)
f
RRDF-98 — — — — 0.7717 1.03 (2.46) 1.03 ± 0.058 a
93 Nb(n,n¢)
f
RRDF-98 — — — — 146.1 2.59 (2.61) 1.001 ± 0.043 a
93 Nb(n,γ)
c
IRDF-90 1.16 9.91 10.00 9.49 — — Thermal: 1.01 ± 0.11 d
Epithermal: 1.17 ± 0.13 d
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