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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
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TABLE 4.3. IRDF-90.2 ( DATA IN A CA
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TABLE 4.4. JENDL/D-99 ( DATA IN A C
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TABLE 4.4. JENDL/D-99 ( DATA IN A C
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TABLE 4.5. UPDATED RRDF-98 ( DATA I
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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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TABLE 6.2. CROSS-SECTIONS IN IRDF-2
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TABLE 6.2. CROSS-SECTIONS IN IRDF-2
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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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- Page 106 and 107: ecommendations found in ASTM practi
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- Page 112 and 113: 9. DECAY DATA AND ISOTOPIC ABUNDANC
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- Page 160 and 161: CONTRIBUTORS TO DRAFTING AND REVIEW
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