International Reactor Dosimetry File 2002 - IAEA Publications

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Appendix III COMPARISON OF THERMAL CROSS-SECTIONS AND RESONANCE INTEGRALS FOR DOSIMETRY REACTIONS A. Trkov IRDF-<strong>2002</strong> contains cross-sections for 66 reactions, of which 17 represent radiative capture. Verification and validation of the cross-section data from various sources are important steps in the selection of the source data and for validation of the final dosimetry library. Therefore, a comparison of the evaluated data from different sources was made using the following: (a) (b) Mughabghab evaluation of the thermal cross-sections and resonance integrals [III.1]; Q 0 values, which are the ratios of the resonance integral to thermal crosssection from the k 0 database for neutron activation analysis (NAA) [III.2]. The Mughabghab compilation, commonly known as BNL-325, is the most comprehensive compilation of thermal cross-sections and resonance integrals and has been recently revised by the author. Activation analysis is in some sense ‘reverse dosimetry’. Well tested and applied in practice, the nuclear data for activation analysis are highly relevant to a dosimetry database. The k 0 standardization method is a variant of activation analysis, and requires the Q 0 value for each nuclide. The Q 0 values for several nuclides have been measured, usually by the cadmium ratio method, which is insensitive to the detector efficiency and the abundance of the nuclide in a natural mixture of an element. The following evaluated nuclear data libraries were considered in the present study: (i) (ii) (iii) (iv) (v) (vi) The old IRDF-90.2 dosimetry library [III.3]; The JENDL-D/99 dosimetry library [III.4]; The latest Japanese JENDL-3.3 evaluated nuclear data library [III.5]; US library ENDF/B-VI Release 8 [III.6]; European Activation <strong>File</strong> EAF-99 [III.7]; The new evaluations for 139 La and 186 W by Zolotarev [III.8]. 115
III.1. THERMAL CROSS-SECTIONS Generally, there is reasonably good agreement between the cross-section values in evaluated nuclear data files at the thermal energy of 0.253 eV, but there are a number of exceptions, which are listed below (see also Table III.1): — 58 Fe: The adopted thermal cross-section is the value re-evaluated by Moxon [III.9], and differs marginally from the latest Mughabghab recommendation (1.30(2) b). JENDL-3.3 data are consistent with the Mughabghab recommendation, while all other evaluations are lower by more than 12% and lower still compared with the old value by Mughabghab of 1.28(5) b [III.10]. — 63 Cu: The uncertainty assigned to the Mughabghab value is very low; JENDL-3.3 data are consistent with the Mughabghab recommendation. — 109 Ag: The observed differences arise because the dosimetry crosssections represent excitation of the metastable state, while Mughabghab gives the total capture cross-section. No corrective action is needed at present. — 115 In: The same argument applies as for 109 Ag. — 139 La: The uncertainty assigned to the thermal capture cross-section by Mughabghab is very small. The value from ENDF/B-VI Release 8 agrees with the latest Mughabghab recommendation, while other evaluated data files adopted the older and lower Mughabghab value. — 181 Ta: The thermal capture cross-section from JENDL-3.3 agrees with the Mughabghab recommendation. — 186 W: The new Mughabghab recommendation for the thermal crosssection of 38.5 b is slightly higher than the old value of 37.9 b. JENDL-D/99 and the Zolotarev evaluation follow the old recommendation. The JENDL-3.3 value is higher than the new Mughabghab recommendation. The value from the new Zolotarev evaluation is closest to the new Mughabghab recommendation. — 232 Th: The data from the evaluated libraries agree, but are slightly higher than the Mughabghab recommendation. — 238 U: The Mughabghab recommendation is slightly lower than the value recommended for the ENDF/B-VI standards. A more detailed investigation indicates that the ENDF/B-VI value is strongly influenced by the measurement of Bigham, which may be incorrect [III.11]. Other recent measurements are consistent (after corrections) with the Mughabghab value. 116
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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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Page 84 and 85: 7. CONSISTENCY TEST OF THE CROSS-SE
Page 86 and 87: TABLE 7.1. REFERENCE NEUTRON FIELDS
Page 88 and 89: Fluence, (E) (MeV -1 ) 10 7 10 6 10
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Page 92 and 93: testing of electronic components an
Page 94 and 95: Table 7.3 details the 34 dosimetry
Page 96 and 97: 7.2. RESULTS OF CONSISTENCY TESTING
Page 98 and 99: TABLE 7.4. RATIO OF SPECTRUM AVERAG
Page 104 and 105: [7.7] SEKINE, T., MAEDA, S., AOYAMA
Page 106 and 107: ecommendations found in ASTM practi
Page 108 and 109: 10 2 Damage (MeV· mb) 10 1 10 0 10
Page 110 and 111: 10 2 Damage (MeV· mb) 10 1 10 0 10
Page 112 and 113: 9. DECAY DATA AND ISOTOPIC ABUNDANC
Page 114 and 115: 9.1.4. Data processing The required
Page 116: Protactinium-231 is stated to have
Page 119 and 120: TABLE I.1. METROLOGY REACTIONS (ACT
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Page 125 and 126: of each neutron energy group. These
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Page 131 and 132: TABLE III.1. COMPARISON OF THERMAL
Page 133 and 134: TABLE III.2. COMPARISON OF CAPTURE
Page 135 and 136: TABLE III.3. COMPARISON OF THE Q 0
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Page 139 and 140: REFERENCES TO APPENDIX III [III.1]
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Page 160 and 161: CONTRIBUTORS TO DRAFTING AND REVIEW
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