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 3.3. THERMAL NEUTRON CROSS-SECTIONS AND RESONANCE INTEGRALS FOR REACTIONS SELECTED<br />
FOR IRDF-<strong>2002</strong> (TEMPERATURE OF 300 K)<br />
Reaction<br />
Material<br />
No.<br />
MT<br />
No.<br />
Library<br />
(selected<br />
evaluation)<br />
Library<br />
cross-section<br />
(2200 m/s)<br />
σ L (m 2 )<br />
Evaluated<br />
experimental<br />
data (2200 m/s)<br />
σ M (m 2 )<br />
Evaluated<br />
experimental<br />
data (2200 m/s)<br />
σ H (m 2 )<br />
Cross-section<br />
ratio<br />
Resonance<br />
integral from<br />
library data<br />
IR L (m 2 )<br />
Evaluated<br />
resonance<br />
integral IR M<br />
(m 2 )<br />
Evaluated<br />
resonance<br />
integral IR H<br />
(m 2 )<br />
Resonance integral<br />
ratio<br />
σ L /σ M σ L /σ H IR L /IR M IR L /IR H<br />
6 Li(n,t) 325 105 IRDF-90 9.42E-26 Not available 9.4(1)E-26 — 1.00 4.27E-26 Not available 4.22(4)E-26 — 1.01<br />
10 B(n,α) 525 107 IRDF-90 3.84E-25 Not available 3.84(1)E-25 — 1.00 1.73E-25 Not available 1.73(1)E-25 — 1.00<br />
23 Na(n,γ)<br />
a<br />
1123 102 IRDF-90 5.29E-29 5.30(5)E-29 — 1.00 — 3.17E-29 3.11(10)E-29 3.0(6)E-29 1.02 1.06<br />
45 Sc(n,γ) 2126 102 IRDF-90 2.73E-27 2.72(2)E-27 2.7E-27 1.00 1.01 1.20E-27 1.20(5)E-27 1.20E-27 1.00 1.00<br />
55 Mn(n,γ) 2525 102 IRDF-90 1.34E-27 1.336(5)E-27 1.33(1)E-27 1.00 1.01 1.18E-27 1.40(3)E-27 1.40(3)E-27 0.84 0.84<br />
58 Fe(n,γ) 2637 102 JENDL/D-99 (u) 1.30E-28 1.30(3)E-28 1.3(1)E-28 1.00 1.00 1.37E-28 1.7(1)E-28 1.3(2)E-28 0.81 1.05<br />
59 Co(n,γ) 2725 102 IRDF-90 3.72E-27 3.718(6)E-27 3.72E-27 1.00 1.00 7.60E-27 7.59(2)E-27 7.4E-27 1.00 1.03<br />
63 Cu(n,γ) 2925 102 IRDF-90 4.47E-28 4.52(2)E-28 4.5(2)E-28 0.99 0.99 4.96E-28 4.97(8)E-28 5.0(1)E-28 1.00 0.99<br />
93 Nb(n,γ)<br />
a<br />
4125 102 IRDF-90 1.16E-28 1.15(5)E-28 1.1E-28 1.01 1.05 9.91E-28 8.5(5)E-28 8.5E-28 1.17 1.17<br />
109 Ag(n,γ)<br />
b<br />
4731 102 IRDF-90 (u) 4.21E-28 — 4.2E-28 — 1.00 6.86E-27 — 7.0E-27 — 0.98<br />
115 In(n,γ)<br />
a,b<br />
4931 102 IRDF-90 1.67E-26 2.02(2)E-26 2.05E-26 — 1.04 2.59E-25 Not available 2.7E-25 — 0.96<br />
139 La(n,γ) 5712 102 RRDF-98 (n) 9.04E-28 9.04(4)E-28 9.2(2)E-28 1.00 0.98 1.20E-27 1.21(6)E-27 1.2(1)E-27 0.99 1.00<br />
181 Ta(n,γ)<br />
a<br />
7328 102 JENDL/D-99 2.07E-27 2.05(5)E-27 2.01E-27 1.01 1.04 6.59E-26 6.60(23)E-26 6.504E-26 1.00 1.01<br />
186 W(n,γ) 7452 102 RRDF-98 (n) 3.85E-27 3.85(5)E-27 3.7(2)E-27 1.00 1.04 4.80E-26 4.85(15)E-26 5.10(50)E-26 0.99 0.94<br />
197 Au(n,γ)<br />
c<br />
7925 102 IRDF-90 9.88E-27 9.865(90)E-27 9.87(10)E-27 1.00 1.00 1.57E-25 1.550(28)E-25 1.55(3)E-25 1.01 1.01<br />
232 Th(n,γ)<br />
a<br />
9040 102 IRDF-90 7.41E-28 7.35(3)E-28 7.37(4)E-28 1.01 1.00 8.56E-27 8.5(3)E-27 8.5(3)E-27 1.01 1.01<br />
235 U(n,f)<br />
d<br />
9228 18 IRDF-90 5.86E-26 Not available 5.86(2)E-26 — 1.01 2.72E-26 Not available 2.75(5)E-26 — 0.99<br />
238 U(n,γ) 9237 102 IRDF-90 2.72E-28 2.680(19)E-28 2.7(1)E-28 1.01 1.00 2.77E-26 2.77(3)E-26 2.77(3)E-26 1.00 1.00<br />
25