Technical Data
fuel-moderator material | 8 wt% uranium 91 wt% zirconium 1 wt% hydrogen |
uranium enrichment | 19.8% Uran-235 |
fuel element dimensions | 3.75 cm in diameter 72.24 cm in length |
cladding | 0.51 mm steel |
active core volume | max. 49.5 cm diameter, 35.56 cm high |
core loading | 3 kg of uranium-235 |
material | graphite with aluminum cladding |
radial thickness | 30.5 cm |
top and bottom thickness | 10.2 cm |
reactor shielding construction | heavy and standard concrete 6.55 m high, 6.19 m wide, 8.76 m long |
reactor tank | 1.98 m in diameter 6.40 m in depth |
radial: | 30.5 cm of graphite; 45.7 cm of water 206 cm of heavy concrete |
vertical: | above the core 4.90 m of water and 10.2 cm graphite; underneath the core 61.0 cm water, 10.2 cm graphite and at least 91 cm standard concrete |
(1) four beam holes 15.2 cm in diameter |
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Thermal power output: | 250 kW |
Fuel element cooling: | natural convection of the tank water below 100 kW, pump circulation cooling above 100 kW |
tank water cooling: | heat exchanger |
thermal flux: | central irradiation tube: 1x1013cm-2s-1 in the irradiation tubes: 1.7x1012 cm-2s-1 |
prompt temperature coefficient: | -1.2x10-4 δk/k°C |
mean prompt neutron lifetime: | 6.0x10-5 s. |
peak power | 250 MW |
prompt pulse energy yield | 10 MW s |
prompt pulse lifetime | 40 ms |
total energy yield | 12 MW s |
minimal period | 10 ms |
maximum reactivity insertion | 1.6% δk/k = 2$ |
maximum repetition frequency | 12/h |
number of fissions during a pulse | 3x1017 |
maximum fuel temperature: | during the pulse 240 °C 9 seconds after the pulse 360 °C |
average during last 5 years | |
power produced (MWh) | 300 |
irradiation experiments | 200 |
beam hole experiments | 15 |
number of reactor pulses | 10 |
number of visitors | 2500 |