International Reactor Dosimetry File 2002 - IAEA Publications
International Reactor Dosimetry File 2002 - IAEA Publications
International Reactor Dosimetry File 2002 - IAEA Publications
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TABLE 6.2. CROSS-SECTIONS IN IRDF-<strong>2002</strong> AND THEIR CHARACTERISTICS (TEMPERATURE OF 300 K) (cont.)<br />
Reaction<br />
Selected<br />
evaluation<br />
Calculated<br />
library crosssection<br />
(2200 m/s)<br />
σ L (b)<br />
Resonance<br />
integral from<br />
library data<br />
IR L (b)<br />
Uncertainty in<br />
library data<br />
Thermal<br />
(%)<br />
Epithermal<br />
(%)<br />
Calculated average<br />
library crosssection<br />
in 252 Uncertainty in<br />
Cf<br />
(%) a C/E<br />
fission (mb) a<br />
181 Ta(n,γ)<br />
c<br />
JENDL/D-99 20.7 659 3.00 3.77 — — Thermal: 1.01 ± 0.04 d<br />
Epithermal: 1.00 ± 0.05 d<br />
186 W(n,γ) RRDF-98 (n) 38.5 480 2.31 3.32 — — Thermal: 1.00 ± 0.03,<br />
d<br />
1.04 ± 0.06 b<br />
Epithermal: 0.99 ± 0.04, d<br />
0.94 ± 0.10 b<br />
197 Au(n,2n) IRDF-90 — — — — 5.747 4.19 (4.65) 1.044 ± 0.052<br />
a<br />
197 Au(n,γ)<br />
g<br />
IRDF-90 98.8 1570 0.14 0.17 — — Thermal: 1.00 ± 0.01, d<br />
1.00 ± 0.01 b<br />
Epithermal: 1.01 ± 0.02, d<br />
1.01 ± 0.02 b<br />
199 Hg(n,n¢)<br />
f<br />
JENDL/D-99 (u) — — — — 248.6 7.82 (7.83) 0.833 ± 0.067 a<br />
204 Pb(n,n¢)<br />
f<br />
RRDF-98 (n) — — — — 20.39 4.57 (4.67) 0.978 ± 0.063 a<br />
232 Th(n,γ)<br />
c<br />
IRDF-90 7.41 85.6 4.33 10.92 — — Thermal: 1.01 ± 0.04, d<br />
1.00 ± 0.04 b<br />
Epithermal: 1.01 ± 0.12, d<br />
1.01 ± 0.12 b<br />
232 Th(n,f) IRDF-90 — — — — 78.55 5.09 (5.11) 0.879 ± 0.052<br />
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