International Reactor Dosimetry File 2002 - IAEA Publications

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INTERNATIONAL REACTOR DOSIMETRY FILE 2002 (IRDF-2002)
The following States are Members of the International Atomic Energy Agency: AFGHANISTAN ALBANIA ALGERIA ANGOLA ARGENTINA ARMENIA AUSTRALIA AUSTRIA AZERBAIJAN BANGLADESH BELARUS BELGIUM BELIZE BENIN BOLIVIA BOSNIA AND HERZEGOVINA BOTSWANA BRAZIL BULGARIA BURKINA FASO CAMEROON CANADA CENTRAL AFRICAN REPUBLIC CHAD CHILE CHINA COLOMBIA COSTA RICA CÔTE D’IVOIRE CROATIA CUBA CYPRUS CZECH REPUBLIC DEMOCRATIC REPUBLIC OF THE CONGO DENMARK DOMINICAN REPUBLIC ECUADOR EGYPT EL SALVADOR ERITREA ESTONIA ETHIOPIA FINLAND FRANCE GABON GEORGIA GERMANY GHANA GREECE GUATEMALA HAITI HOLY SEE HONDURAS HUNGARY ICELAND INDIA INDONESIA IRAN, ISLAMIC REPUBLIC OF IRAQ IRELAND ISRAEL ITALY JAMAICA JAPAN JORDAN KAZAKHSTAN KENYA KOREA, REPUBLIC OF KUWAIT KYRGYZSTAN LATVIA LEBANON LIBERIA LIBYAN ARAB JAMAHIRIYA LIECHTENSTEIN LITHUANIA LUXEMBOURG MADAGASCAR MALAYSIA MALI MALTA MARSHALL ISLANDS MAURITANIA MAURITIUS MEXICO MONACO MONGOLIA MOROCCO MOZAMBIQUE MYANMAR NAMIBIA NETHERLANDS NEW ZEALAND NICARAGUA NIGER NIGERIA NORWAY PAKISTAN PANAMA PARAGUAY PERU PHILIPPINES POLAND PORTUGAL QATAR REPUBLIC OF MOLDOVA ROMANIA RUSSIAN FEDERATION SAUDI ARABIA SENEGAL SERBIA SEYCHELLES SIERRA LEONE SINGAPORE SLOVAKIA SLOVENIA SOUTH AFRICA SPAIN SRI LANKA SUDAN SWEDEN SWITZERLAND SYRIAN ARAB REPUBLIC TAJIKISTAN THAILAND THE FORMER YUGOSLAV REPUBLIC OF MACEDONIA TUNISIA TURKEY UGANDA UKRAINE UNITED ARAB EMIRATES UNITED KINGDOM OF GREAT BRITAIN AND NORTHERN IRELAND UNITED REPUBLIC OF TANZANIA UNITED STATES OF AMERICA URUGUAY UZBEKISTAN VENEZUELA VIETNAM YEMEN ZAMBIA ZIMBABWE The Agency’s Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The Headquarters of the Agency are situated in Vienna. Its principal objective is “to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world’’.
Page 4 and 5: TECHNICAL REPORTS SERIES No. 452 IN
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
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 78 and 79:
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Page 82 and 83:
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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 100 and 101:
Page 102 and 103:
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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130
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CONTRIBUTORS TO DRAFTING AND REVIEW
Page 162:
CONTRIBUTORS TO DRAFTING AND REVIEW
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