International Reactor Dosimetry File 2002 - IAEA Publications

More documents

Recommendations

Info

TABLE 7.1. REFERENCE NEUTRON FIELDS CONSIDERED FOR THE VALIDATION OF IRDF- 2002 Neutron field Ref. ACRR central cavity [7.4] SPR-III central cavity [7.5] MDRF [7.6] JOYO [7.7, 7.8] JMTR [7.8, 7.9] YAYOI [7.8] CFRMF [7.8] ISNF [7.8] Sigma–sigma (Â–Â) [7.8] Note: ACRR: Annular Core Research Reactor; SPR-III: Sandia Pulsed Reactor-III; MDRF: Materials Dosimetry Reference Facility; JOYO: experimental fast reactor; JMTR: Japan Materials Testing Reactor; YAYOI: fast neutron source reactor; CFRMF: Coupled Fast Reactivity Measurement Facility; ISNF: Intermediate Energy Standard Neutron Field; sigma–sigma: coupled thermal/ fast uranium and boron carbide spherical assembly. neutron fields, the set of reference neutron fields used for this validation will expand in future releases of the IRDF-2002 dosimetry library. The following sections provide reference citations available in the literature and baseline characterization details for the fast neutron field and the water moderated neutron field used for this validation procedure. 7.1.1. ACRR reference neutron field The ACRR is a water moderated test reactor with a dry central cavity and a fuelled external cavity. A total of 236 cylindrical fuel elements contain a unique BeO–UO 2 fuel with 35% enriched 235 U that allows operation at fuel temperatures of up to 1400°C in pulse and steady state modes. This reactor is capable of steady state operation at 2 MW, intermittent operation at 4 MW, and pulsed operation with a maximum pulse of 300 MJ, a peak power of 30 000 MW, and a pulse width of 6.5 ms. The reactor core is located in a 3.1 m diameter and 8.5 m deep pool, with a 22.5 cm (9 in) diameter dry central cavity that supports 73
large test fixtures and provides good uniformity. Figure 7.1 shows the ACRR reactor and the dry experimental cavity. A more comprehensive description of this reference field appears in Ref. [7.4]. Details of the radiation transport models and 640 group representation of the neutron spectrum in the ACRR central cavity appear in Ref. [7.10]. Figure 7.2 shows the calculated spectrum in a typical logarithmic number fluence plot (written as Φ(E) or dn/dE). The calculated spectrum in a linear lethargy plot is shown in Fig. 7.3 (notated as EΦ(E), but often notated as Φ(μ) or dE/dE). Equal areas under the curve in the lethargy plot (with linear y axis and logarithmic energy x axis or lethargy) correspond to equal neutron content. Figure 7.3 shows some prominent resonance absorption structure in the 0.5–2 MeV neutron energy region. Excellent sampling statistics in the Monte Carlo radiation transport calculation (
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 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 84 and 85: 7. CONSISTENCY TEST OF THE CROSS-SE
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
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]
Page 141 and 142:
128
Page 143 and 144:
130
Page 145 and 146:
132
Page 147 and 148:
134
Page 149 and 150:
136
Page 151 and 152:
138
Page 153 and 154:
140
Page 155 and 156:
142
Page 157 and 158:
144
Page 160 and 161:
CONTRIBUTORS TO DRAFTING AND REVIEW
Page 162:
CONTRIBUTORS TO DRAFTING AND REVIEW
show all

International Reactor Dosimetry File 2002 - IAEA Publications

You also want an ePaper? Increase the reach of your titles

Delete template?

Save as template?