International Reactor Dosimetry File 2002 - IAEA Publications

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TABLE 6.1. INTEGRAL CHARACTERISTICS OF THE FAST NEUTRON CROSS-SECTIONS AS CANDIDATES FOR IRDF-<strong>2002</strong> (CROSS-SECTIONS AVERAGED OVER THE WATT FISSION SPECTRUM) (cont.) Reaction Library Cross-section (m 2 ) Relative standard deviation of a (%) 238 U(n,f) IRDF-90 2.997E-29 0.54 238 U(n,f) JENDL/D-99 3.034E-29 2.09 Cross-section averaged over the Watt fission spectrum. a Weighted with a typical MTR spectrum from 1.05 MeV to 20 MeV. b Metastable state of the product nuclide. (u): Updated data. (n): New data. 61
TABLE 6.2. CROSS-SECTIONS IN IRDF-<strong>2002</strong> AND THEIR CHARACTERISTICS (TEMPERATURE OF 300 K) Reaction Selected evaluation Calculated library crosssection (2200 m/s) σ L (b) Resonance integral from library data IR L (b) Uncertainty in library data Thermal (%) Epithermal (%) Calculated average library crosssection in 252 Uncertainty in Cf (%) a C/E fission (mb) a 6 Li(n,t) IRDF-90 942 427 0.14 0.14 — — Thermal: 1.00 ± 0.01 b Epithermal: 1.00 ± 0.01 b 10 B(n,α) IRDF-90 3840 1730 0.16 0.16 — — Thermal: 1.00 ± 0.01 b Epithermal: 0.99 ± 0.01 b 19 F(n,2n) RRDF-98 (u) — — — — 1.627E-2 2.92 (5.33) 1.009 ± 0.064 a 23 Na(n,γ) c IRDF-90 0.529 0.317 2.00 3.14 — — Thermal: 1.00 ± 0.02 d Epithermal: 0.97 ± 0.04 d 23 Na(n,2n) JENDL/D-99 (u) — — — — 8.611E-3 3.90 (8.16) No experimental data in 252 Cf fission field 24 Mg(n,p) IRDF-90 — — — — 2.160 2.24 (2.75) 1.082 ± 0.040 a 27 Al(n,p) RRDF-98 (n) — — — — 4.912 2.06 (2.37) 1.007 ± 0.032 a 27 Al(n,α) IRDF-90 — — — — 1.038 1.36 (2.12) 1.022 ± 0.026 a 31 P(n,p) IRDF-90 — — — — 30.68 3.58 (3.65) No experimental data in 252 Cf fission field 32 S(n,p) IRDF-90 — — — — 70.30 3.60 (3.67) 0.969 ± 0.049 a 45 Sc(n,γ) IRDF-90 27.3 12.0 0.73 0.76 — — Thermal: 1.00 ± 0.01 d Epithermal: 1.00 ± 0.04 d 62
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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
Page 24 and 25: TABLE 2.2. MEASURED AND CALCULATED
Page 26 and 27: [2.24] KOBAYASHI, K., KIMURA, I., M
Page 28 and 29: from ENDF/B-VI Release 8, JEFF-3.0
Page 30 and 31: TABLE 3.1. REACTIONS FROM THE VARIO
Page 32 and 33: Fluence rate per unit energy (m -2
Page 34 and 35: TABLE 3.2. COMPARISON OF THE INTEGR
Page 36 and 37: — 10 B(n,α) 7 Li and 6 Li(n,t) 4
Page 38 and 39: TABLE 3.3. THERMAL NEUTRON CROSS-SE
Page 40 and 41: TABLE 3.4. RELATIVE STANDARD DEVIAT
Page 42 and 43: [3.14] HOLDEN, N.E., “Neutron sca
Page 44 and 45: The rigorous inclusion of all uncer
Page 46 and 47: TABLE 4.1. C/E VALUES IN THE CALIFO
Page 48 and 49: 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 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 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
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of each neutron energy group. These
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activation rate for the product iso
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III.1. THERMAL CROSS-SECTIONS Gener
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TABLE III.1. COMPARISON OF THERMAL
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TABLE III.2. COMPARISON OF CAPTURE
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TABLE III.3. COMPARISON OF THE Q 0
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— 50 Cr: Compared with the Mughab
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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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