TABLE III.4. CANDIDATE EVALUATED DATA FILES FOR THE IRDF-<strong>2002</strong> DOSIMETRY LIBRARY Nuclide Candidate data files 23 Na ENDF/B-VI Release 8 45 Sc ENDF/B-VI Release 8; IRDF-90.2; JENDL-3.3 50 Cr None (resonance integral inconsistency) 55 Mn None 58 Fe JENDL-3.3; JENDL-D/99 59 Co All 63 Cu All 93 Nb JENDL-3.3 109 Ag Metastable product: no comparison 115 In JENDL-D/99; JENDL-3.3 139 La ENDF/B-VI Release 8; JENDL-3.3; Zolotarev 151 Eu None (resonance integral inconsistency) 181 Ta JENDL-3.3 186 W Zolotarev 197 Au JENDL-D/99; ENDF/B-VI Release 8 232 Th All 238 U All thermal cross-sections and the resonance integrals with the Mughabghab recommendations and the k 0 database. This analysis is intended to complement other selection criteria such as format correctness, completeness, internal consistency of other parameters and availability of covariance information. Problem areas exist that need to be resolved: — 50 Cr: The discrepancy between the Mughabghab recommendation and resonance parameter data in the files needs to be resolved. — 55 Mn: The discrepancy between the Mughabghab recommendation and resonance parameter data in the files needs to be resolved. — 58 Fe: The Q 0 value from the k 0 database suggests preference for JENDL- 3.3 as the source data; the resonance integral should be reassessed. — 151 Eu: The thermal capture cross-section is practically the same in all data sources. Although the resonance integral is less important, differences of almost a factor of three between measurements deserve further attention. 125
REFERENCES TO APPENDIX III [III.1] MUGHABGHAB, S.F., Thermal Neutron Capture Cross Sections, Resonance Integrals and g-factors, Rep. INDC(NDS)-440, <strong>IAEA</strong>, Vienna (2003). [III.2] DE CORTE, F., The k 0 Standardization Method, PhD Thesis, Rijksuniversiteit, Gent (1987). [III.3] IRDF-90 Version 2 — The <strong>International</strong> <strong>Reactor</strong> <strong>Dosimetry</strong> <strong>File</strong> (KOCH- EROV, N.P., McLAUGHLIN, P.K., Eds), Rep. <strong>IAEA</strong>-NDS-141, Rev. 2, <strong>IAEA</strong>, Vienna (1993). [III.4] KOBAYASHI, K., et al., JENDL <strong>Dosimetry</strong> <strong>File</strong> 99, Rep. JAERI 1344, Japan Atomic Energy Research Institute, Tokai-mura (<strong>2002</strong>). [III.5] SHIBATA, K., et al., Japanese Evaluated Nuclear Data Library, Version 3, Revision 3, JENDL-3.3, J. Nucl. Sci. Technol. 39 (<strong>2002</strong>) 1125. [III.6] ROSE, P.F. (Ed.), ENDF/B-VI Summary Documentation, Rep. BNL-NCS- 17541 (ENDF-201), Brookhaven Natl Lab., NY (1991); Data Library ENDF/B- VI Release 8, update 2001, by the US National Nuclear Data Center on behalf of the Cross-section Evaluation Working Group. [III.7] SUBLET, J.-C., et al., The European Activation <strong>File</strong>: EAF-99 Cross Section Library, Rep. FUS 408, UKAEA, Culham, UK (1998). [III.8] ZOLOTAREV, K.I., Institute of Physics and Power Engineering, Obninsk, personal communication. [III.9] MOXON, M.C., The Thermal Activation Cross Section of Fe, Rep. JEF/DOC- 831, NEA Data Bank, Issy-les-Moulinaux, France (2000). [III.10] MUGHABGHAB, S.F., DIVADEENAM, M., HOLDEN, N.E., Neutron Cross Sections, Vol. 1, Neutron Resonance Parameters and Thermal Cross Sections, Parts A and B, Academic Press, New York (1981). [III.11] TRKOV, A., et al., Revisiting the U-238 thermal capture cross section and gamma-ray emission probabilities from Np-239 decay, Nucl. Sci. Eng. 150 (2005) 336. [III.12] SIMONITS, A., DE CORTE, F., EL NIMR, T., MOENS, L., HOSTE, J., Comparative study of measured and critically evaluated resonance integral to thermal cross-section ratios, Part II, J. Radioanal. Nucl. Chem. 81 (1984) 397. 126
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INTERNATIONAL REACTOR DOSIMETRY FIL
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TECHNICAL REPORTS SERIES No. 452 IN
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FOREWORD An accurate and complete k
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Contributing authors O. Bersillon C
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5.1. Plots of experimental data and
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1. INTRODUCTION R. Paviotti-Corcuer
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(b) (c) Pointwise data: (i) All dos
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REFERENCES TO SECTION 1 [1.1] ZIJP,
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cross-sections, and as a consequenc
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TABLE 2.1. MEASURED AND CALCULATED
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TABLE 2.2. MEASURED AND CALCULATED
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[2.24] KOBAYASHI, K., KIMURA, I., M
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from ENDF/B-VI Release 8, JEFF-3.0
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TABLE 3.1. REACTIONS FROM THE VARIO
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Fluence rate per unit energy (m -2
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TABLE 3.2. COMPARISON OF THE INTEGR
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— 10 B(n,α) 7 Li and 6 Li(n,t) 4
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TABLE 3.3. THERMAL NEUTRON CROSS-SE
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TABLE 3.4. RELATIVE STANDARD DEVIAT
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[3.14] HOLDEN, N.E., “Neutron sca
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The rigorous inclusion of all uncer
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TABLE 4.1. C/E VALUES IN THE CALIFO
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TABLE 4.3. IRDF-90.2 ( DATA IN A CA
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TABLE 4.3. IRDF-90.2 ( DATA IN A CA
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TABLE 4.4. JENDL/D-99 ( DATA IN A C
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TABLE 4.4. JENDL/D-99 ( DATA IN A C
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TABLE 4.5. UPDATED RRDF-98 ( DATA I
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REFERENCES TO SECTION 4 [4.1] KOCHE
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neutron yield substantially. Furthe
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TABLE 5.1. CROSS-SECTION EVALUATION
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TABLE 5.1. CROSS-SECTION EVALUATION
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— 58 Ni(n,2n) 57 Ni: The IRDF, JE
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— 238 U(n,γ) 239 U(β - ) 239 Np
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(i) (ii) (iii) (iv) (v) Only diagon
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TABLE 6.1. INTEGRAL CHARACTERISTICS
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TABLE 6.1. INTEGRAL CHARACTERISTICS
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TABLE 6.2. CROSS-SECTIONS IN IRDF-2
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TABLE 6.2. CROSS-SECTIONS IN IRDF-2
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TABLE 6.2. CROSS-SECTIONS IN IRDF-2
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TABLE 6.2. CROSS-SECTIONS IN IRDF-2
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7. CONSISTENCY TEST OF THE CROSS-SE
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TABLE 7.1. REFERENCE NEUTRON FIELDS
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