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
54 Fe(n,2n) RRDF-98 (u) — — — — 3.498E-3 4.87 (10.71) No experimental data in
252 Cf fission field
54 Fe(n,α) RRDF-98 (u) — — — — 1.113 3.18 (3.48) No experimental data in
252 Cf fission field
54 Fe(n,p) IRDF-90 — — — — 88.16 2.09 (2.23) 1.015 ± 0.026
a
56 Fe(n,p) RRDF-98 (u) — — — — 1.475 2.61 (2.99) 1.007 ± 0.035
a
58 Fe(n,γ) JENDL/D-99 (u) 1.30 1.37 12.60 8.70 — — Thermal: 1.00 ± 0.13,
d
1.00 ± 0.15 b
Epithermal: 0.81 ± 0.08, d
1.05 ± 0.18 b
59 Co(n,2n) IRDF-90 — — — — 0.4228 2.67 (4.20) 1.044 ± 0.051
a
59 Co(n,α) RRDF-98 (u) — — — — 0.2212 3.54 (3.87) 0.997 ± 0.043
a
59 Co(n,γ) IRDF-90 37.2 76.0 0.66 0.77 — — Thermal: 1.00 ± 0.01
d
Epithermal: 1.00 ± 0.01 d
58 Ni(n,2n) JEFF-3.0 — — — — 9.256E-3 2.72 (6.67) 1.034 ± 0.078
a
58 Ni(n,p) RRDF-98 (n) — — — — 117.5 1.74 (1.89) 1.000 ± 0.023
a
60 Ni(n,p) ENDF/B-VI — — — — 2.494 10.11 (10.20) 1.044 ± 0.121
a
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