Configuration | Neutron flux density (cm−2·s−1) | |
---|---|---|
Empty layout | (1.28 ± 0.11) × 109 | (2.38 ± 0.20) × 108 |
Layout with topaz | (8.76 ± 0.62) × 108 | (2.45 ± 0.19) × 108 |
Model with boron carbide screen and topaz | (1.72 ± 0.14) × 108 | (2.15 ± 0.18) × 108 |
Layout with sandwich screen and topaz | (1.54 ± 0.62) × 108 | (2.28 ± 0.17) × 108 |
Detector type | Gold | Indium |
---|---|---|
Neutron energy region | Thermal | Fast |
Energy threshold | 0 ≤ |
|
Nuclear reactions | 197Au( |
115In( |
Half-life | 2.696 days | 4.486 h |
Reaction cross-section (barn) | 98.7 | 0.286 |
Reactor type | Tank |
---|---|
Thermal power (W) | 100 |
Reflector | Light water and/or beryllium |
Moderator | Light water and/or beryllium |
Maximum thermal neutron flux (cm−2·s−1) | 3 × 109 |
Maximum fast neutron flux (cm−2·s−1) | 2 × 108 |
Fuel composition | UO2 + Al |
U-235 enrichment (%) | 19.7 |
Experimental channel’s diameter (mm) | 65, 96, 140 |
Layout type | Specific activity (Bq·g−1) | ||
---|---|---|---|
Ga-72 ( |
Na-24 ( |
Ta-182 ( |
|
Layout without a screen | 1290 ± 70 | 28 658 ± 1146 | 23 ± 3 |
Layout with boron carbide screen | 316 ± 16 | 12 600 ± 447 | 15 ± 4 |
Layout with sandwich screen | 302 ± 43 | 13 666 ± 548 | – |