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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 />

67

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