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International Reactor Dosimetry File 2002 - IAEA Publications

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TABLE III.4. CANDIDATE EVALUATED DATA<br />

FILES FOR THE IRDF-<strong>2002</strong> DOSIMETRY LIBRARY<br />

Nuclide<br />

Candidate data files<br />

23 Na ENDF/B-VI Release 8<br />

45 Sc ENDF/B-VI Release 8; IRDF-90.2; JENDL-3.3<br />

50 Cr None (resonance integral inconsistency)<br />

55 Mn None<br />

58 Fe JENDL-3.3; JENDL-D/99<br />

59 Co All<br />

63 Cu All<br />

93 Nb JENDL-3.3<br />

109 Ag Metastable product: no comparison<br />

115 In JENDL-D/99; JENDL-3.3<br />

139 La ENDF/B-VI Release 8; JENDL-3.3; Zolotarev<br />

151 Eu None (resonance integral inconsistency)<br />

181 Ta JENDL-3.3<br />

186 W Zolotarev<br />

197 Au JENDL-D/99; ENDF/B-VI Release 8<br />

232 Th All<br />

238 U All<br />

thermal cross-sections and the resonance integrals with the Mughabghab<br />

recommendations and the k 0 database. This analysis is intended to complement<br />

other selection criteria such as format correctness, completeness, internal<br />

consistency of other parameters and availability of covariance information.<br />

Problem areas exist that need to be resolved:<br />

— 50 Cr: The discrepancy between the Mughabghab recommendation and<br />

resonance parameter data in the files needs to be resolved.<br />

— 55 Mn: The discrepancy between the Mughabghab recommendation and<br />

resonance parameter data in the files needs to be resolved.<br />

— 58 Fe: The Q 0 value from the k 0 database suggests preference for JENDL-<br />

3.3 as the source data; the resonance integral should be reassessed.<br />

— 151 Eu: The thermal capture cross-section is practically the same in all data<br />

sources. Although the resonance integral is less important, differences of<br />

almost a factor of three between measurements deserve further attention.<br />

125

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