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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— 10 B(n,α) 7 Li and 6 Li(n,t) 4 He: The uncertainty of the library crosssections<br />
in the intermediate neutron energy region is too small (not<br />
realistic) compared with the corresponding C/E values (or the<br />
library data deviate significantly from the experimental values).<br />
— 23 Na(n,γ) 24 Na: The uncertainty information contains only a diagonal<br />
matrix — a new evaluation is required.<br />
— 55 Mn(n,γ) 56 Mn: The C/E value for the resonance integral deviates by<br />
16% from unity — excessive when compared with the related<br />
uncertainty values; a new cross-section evaluation is needed in the<br />
intermediate neutron energy region.<br />
— 58 Fe(n,γ) 59 Fe: The C/E value for the resonance integral with the<br />
Mughabghab data deviates by 19% from unity. A large difference is<br />
also found between the recommended experimental data for the<br />
sources considered. Clarification of this discrepancy is necessary<br />
because this reaction is one of the most frequently used detectors in<br />
reactor dosimetry. A new cross-section evaluation in the intermediate<br />
neutron energy region should also be considered.<br />
— 93 Nb(n,γ) 94 Nb: The C/E value for the resonance integral deviates by<br />
17% from unity; furthermore, the uncertainty information contains<br />
only a diagonal matrix — a new evaluation is required.<br />
— 109 Ag(n,γ) 110 Ag m : Mughabghab data represent the sum of the<br />
reaction cross-sections leading to 110 Ag m+g , while the evaluated data<br />
libraries contain only cross-section data for the 109 Ag(n,γ) 110 Ag m<br />
reaction. Therefore, no comparison with the Mughabghab data was<br />
possible.<br />
— 115 In(n,γ) 116 In m : In the present library the cross-section leading to the<br />
metastable states of the product nucleus 116 In is given; uncertainty<br />
information contains only a diagonal matrix — a new evaluation is<br />
required.<br />
— 181 Ta(n,γ) 182 Ta: The uncertainty information contains only a diagonal<br />
matrix — a new evaluation is required.<br />
— 197 Au(n,γ) 198 Au: The available uncertainty information for this<br />
reaction is not reliable; similar data have been withdrawn from<br />
ENDF/B-VI. Uncertainty data in IRDF-90 were derived from the<br />
same source — a new evaluation is required.<br />
— 232 Th(n,γ) 233 Th: The uncertainty information below 15 eV is defined<br />
only in terms of a diagonal matrix — a new evaluation is required.<br />
— 235 U(n,f): The uncertainty information has been declared to be<br />
unreliable, and has been withdrawn from ENDF/B-VI. Data in<br />
IRDF-90 have the same origin — a new evaluation is required.<br />
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