International Reactor Dosimetry File 2002 - IAEA Publications

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TECHNICAL REPORTS SERIES No. 452 INTERNATIONAL REACTOR DOSIMETRY FILE 2002 (IRDF-2002) INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 2006
COPYRIGHT NOTICE All IAEA scientific and technical publications are protected by the terms of the Universal Copyright Convention as adopted in 1952 (Berne) and as revised in 1972 (Paris). The copyright has since been extended by the World Intellectual Property Organization (Geneva) to include electronic and virtual intellectual property. Permission to use whole or parts of texts contained in IAEA publications in printed or electronic form must be obtained and is usually subject to royalty agreements. Proposals for non-commercial reproductions and translations are welcomed and considered on a case-by-case basis. Enquiries should be addressed to the IAEA Publishing Section at: Sales and Promotion, Publishing Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 1400 Vienna, Austria fax: +43 1 2600 29302 tel.: +43 1 2600 22417 email: sales.publications@iaea.org http://www.iaea.org/books © IAEA, 2006 Printed by the IAEA in Austria November 2006 STI/DOC/010/452 IAEA Library Cataloguing in Publication Data International Reactor Dosimetry File 2002 : IRDF-2002 . — Vienna : International Atomic Energy Agency, 2006. p. ; 24 cm. — (Technical reports series, ISSN 0074–1914 ; 452) STI/DOC/010/452 ISBN 92–0–105106–9 Includes bibliographical references. 1. Neutrons — Measurement. 2. Neutron cross sections — Measurement. 3. Radiation dosimetry. I. International Atomic Energy Agency. II. Series: Technical reports series (International Atomic Energy Agency) ; 452. IAEAL 06–00460
Page 2 and 3: INTERNATIONAL REACTOR DOSIMETRY FIL
Page 6 and 7: FOREWORD An accurate and complete k
Page 9 and 10: Contributing authors O. Bersillon C
Page 11 and 12: 5.1. Plots of experimental data and
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
Page 60 and 61:
neutron yield substantially. Furthe
Page 62 and 63:
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
Page 68 and 69:
— 238 U(n,γ) 239 U(β - ) 239 Np
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(i) (ii) (iii) (iv) (v) Only diagon
Page 72 and 73:
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
Page 86 and 87:
TABLE 7.1. REFERENCE NEUTRON FIELDS
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Fluence, (E) (MeV -1 ) 10 7 10 6 10
Page 90 and 91:
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
Page 96 and 97:
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
Page 106 and 107:
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
Page 116:
Protactinium-231 is stated to have
Page 119 and 120:
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
Page 139 and 140:
REFERENCES TO APPENDIX III [III.1]
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130
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144
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CONTRIBUTORS TO DRAFTING AND REVIEW
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CONTRIBUTORS TO DRAFTING AND REVIEW
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