International Reactor Dosimetry File 2002 - IAEA Publications

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CONTENTS 1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 R. Paviotti-Corcuera, E.M. Zsolnay 1.1. Contents of the library . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 REFERENCES TO SECTION 1 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2. NEW RUSSIAN EVALUATIONS FOR IRDF-2002 . . . . . . . . . . . . 6 K.I. Zolotarev REFERENCES TO SECTION 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 3. SELECTION OF CANDIDATE CROSS-SECTIONS FOR IRDF-2002 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 E.M. Zsolnay, H.J. Nolthenius 3.1. Analysis of the data from recent national reactor dosimetry files and new evaluations . . . . . . . . . . . . . . . . . . . . . . 14 3.2. Preliminary selection of cross-sections in the thermal and epithermal neutron energy region for IRDF-2002, and characterization of the selected data . . . . . . . . . . . . . . . . . . . . . . 16 3.2.1. Selection procedure and results . . . . . . . . . . . . . . . . . . . 16 3.2.1.1. Selection procedure . . . . . . . . . . . . . . . . . . . . . 18 3.2.1.2. Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 3.2.2. Characterization of the selected cross-section data . . . 22 3.3. Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 REFERENCES TO SECTION 3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 4. RESPONSE OF ACTIVATION REACTIONS IN THE NEUTRON FIELD OF CALIFORNIUM-252 SPONTANEOUS FISSION . . . 30 W. Mannhart REFERENCES TO SECTION 4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45 5. EVALUATION OF CROSS-SECTIONS AT 14 MeV FOR IRDF-2002 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 L.R. Greenwood
5.1. Plots of experimental data and evaluated cross-sections . . . . . 46 5.2. Detailed comments on the candidate cross-section libraries near 14 MeV . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 REFERENCES TO SECTION 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 6. FINAL SELECTION OF CROSS-SECTIONS FOR IRDF-2002, AND CHARACTERIZATION OF THE SELECTED DATA . . . 56 E.M. Zsolnay, H.J. Nolthenius REFERENCES TO SECTION 6 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 70 7. CONSISTENCY TEST OF THE CROSS-SECTION DATA IN REFERENCE NEUTRON FIELDS . . . . . . . . . . . . . . . . . . . . . . . . . 71 P.J. Griffin 7.1. Description of selected reference neutron fields . . . . . . . . . . . . 72 7.1.1. ACRR reference neutron field . . . . . . . . . . . . . . . . . . . . 73 7.1.2. SPR-III reference neutron field . . . . . . . . . . . . . . . . . . . 78 7.2. Results of consistency testing . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83 7.3. Summary of the validation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 90 REFERENCES TO SECTION 7 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 90 8. RADIATION DAMAGE FILES AND COMPUTER CODES . . . 92 P.J. Griffin, L.R. Greenwood 8.1. Iron dpa (light water reactor pressure vessel damage) . . . . . . . 92 8.2. Silicon arsenide dpa (electronics damage) . . . . . . . . . . . . . . . . . 93 8.3. Gallium arsenide dpa (electronics damage) . . . . . . . . . . . . . . . . 94 REFERENCES TO SECTION 8 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 97 9. DECAY DATA AND ISOTOPIC ABUNDANCES FOR DOSIMETRY APPLICATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 O. Bersillon 9.1. Decay data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 9.1.1. Selection of radionuclides . . . . . . . . . . . . . . . . . . . . . . . . 99 9.1.2. Type of data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 100 9.1.3. Origin of the data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 100
Page 2 and 3: INTERNATIONAL REACTOR DOSIMETRY FIL
Page 4 and 5: TECHNICAL REPORTS SERIES No. 452 IN
Page 6 and 7: FOREWORD An accurate and complete k
Page 9: Contributing authors O. Bersillon C
Page 14 and 15: 1. INTRODUCTION R. Paviotti-Corcuer
Page 16 and 17: (b) (c) Pointwise data: (i) All dos
Page 18 and 19: REFERENCES TO SECTION 1 [1.1] ZIJP,
Page 20 and 21: cross-sections, and as a consequenc
Page 22 and 23: 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
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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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7. CONSISTENCY TEST OF THE CROSS-SE
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TABLE 7.1. REFERENCE NEUTRON FIELDS
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Fluence, (E) (MeV -1 ) 10 7 10 6 10
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TABLE 7.2. SPECTRUM AVERAGED DOSIME
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testing of electronic components an
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Table 7.3 details the 34 dosimetry
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7.2. RESULTS OF CONSISTENCY TESTING
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TABLE 7.4. RATIO OF SPECTRUM AVERAG
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[7.7] SEKINE, T., MAEDA, S., AOYAMA
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ecommendations found in ASTM practi
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10 2 Damage (MeV· mb) 10 1 10 0 10
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10 2 Damage (MeV· mb) 10 1 10 0 10
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9. DECAY DATA AND ISOTOPIC ABUNDANC
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9.1.4. Data processing The required
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Protactinium-231 is stated to have
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TABLE I.1. METROLOGY REACTIONS (ACT
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For the convenience of the metrolog
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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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