International Reactor Dosimetry File 2002 - IAEA Publications

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TABLE 7.4. RATIO OF SPECTRUM AVERAGED CROSS-SECTIONS TO MONITOR THE Ni58p REACTION (cont.) Reaction number IRDF-<strong>2002</strong> reaction C/E ratio b Cover a Comments ACRR SPR-III 35 Cu63a — — Need data in reference fields. Problems with interference reactions. 36 Cu652 — — Need data in reference fields. Problems with interference reactions. 37 Zn64p [Cd] 1.05 ± 5.8% 1.07 ± 6.6% Good consistency. 38 As752 — — Need data in reference fields. 39 Y892 — — Need data in reference fields. 40 Zr902 [Cd] NA 1.03 ± 7.1% Good consistency. Interference thermal neutron reactions suspected in ACRR data. 41 Nb932 [Cd] 1.05 ± 7.0% — Good consistency. 42 Nb93n — — Soft low probability photon makes test data difficult to acquire. Transfer calibration of beta may be used. Need data in reference field. 43 Nb93g [Cd] 1.08 ± 12.7% — Good consistency. 44 Rh103n — — Need data in reference fields. 45 Ag109g NA — Self-shielding correction must be applied to ACRR data. 46 In1152 — — Need data in reference fields. 47 In115n Bare — 1.04 ± 3.4% Good consistency. [Cd] 1.04 ± 7.5% — 87
TABLE 7.4. RATIO OF SPECTRUM AVERAGED CROSS-SECTIONS TO MONITOR THE Ni58p REACTION (cont.) Reaction number IRDF-<strong>2002</strong> reaction C/E ratio b Cover a Comments ACRR SPR-III 48 In115g Bare 1.100 ± 9.3% — Adequate agreement. Cadmium cross-section problem. [Cd] 1.188 ± 10.3% 1.26 ± 7.6% 49 I1272 — — Need data in reference fields. 50 La139g — — Need data in reference fields. 51 Pr1412 — — Need data in reference fields. 52 Tm1692 — — Need data in reference fields. 53 Ta181 — — Need data in reference fields. 54 W186g Bare NA — Self-shielding corrections must be applied to ACRR data. 55 Au1972 — — Need data in reference fields. 56 Au197g Bare 0.9887 ± 7.5% 1.02 ± 7.6% Good consistency. [Cd] 1.016 ± 7.7% 1.07 ± 7.0% [Fi] 0.894 ± 6.3% — 57 Ho199n — — Need data in reference fields. 58 Pb204n — — Need data in reference fields. 59 Th232g — — Need data in reference fields. 60 Th232f — — Need data in reference fields. 61 U235f [Cdna] — 1.04 ± 4.6% Good consistency. [Fi] 1.03 ± 3.97% 1.08 ± 4.6% 88
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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
Page 50 and 51: TABLE 4.3. IRDF-90.2 ( DATA IN A CA
Page 52 and 53: TABLE 4.4. JENDL/D-99 ( DATA IN A C
Page 54 and 55: TABLE 4.4. JENDL/D-99 ( DATA IN A C
Page 56 and 57: TABLE 4.5. UPDATED RRDF-98 ( DATA I
Page 58 and 59: REFERENCES TO SECTION 4 [4.1] KOCHE
Page 60 and 61: neutron yield substantially. Furthe
Page 62 and 63: TABLE 5.1. CROSS-SECTION EVALUATION
Page 64 and 65: TABLE 5.1. CROSS-SECTION EVALUATION
Page 66 and 67: — 58 Ni(n,2n) 57 Ni: The IRDF, JE
Page 68 and 69: — 238 U(n,γ) 239 U(β - ) 239 Np
Page 70 and 71: (i) (ii) (iii) (iv) (v) Only diagon
Page 72 and 73: TABLE 6.1. INTEGRAL CHARACTERISTICS
Page 74 and 75: TABLE 6.1. INTEGRAL CHARACTERISTICS
Page 76 and 77: TABLE 6.2. CROSS-SECTIONS IN IRDF-2
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
Page 90 and 91: TABLE 7.2. SPECTRUM AVERAGED DOSIME
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 102 and 103: 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
Page 121 and 122: For the convenience of the metrolog
Page 123 and 124: Such approximate calculations are n
Page 125 and 126: of each neutron energy group. These
Page 127 and 128: activation rate for the product iso
Page 129 and 130: III.1. THERMAL CROSS-SECTIONS Gener
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
Page 137 and 138: — 50 Cr: Compared with the Mughab
Page 139 and 140: REFERENCES TO APPENDIX III [III.1]
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CONTRIBUTORS TO DRAFTING AND REVIEW
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CONTRIBUTORS TO DRAFTING AND REVIEW
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