A Review of Criticality Accidents A Review of Criticality Accidents
A Review of Criticality Accidents A Review of Criticality Accidents
A Review of Criticality Accidents A Review of Criticality Accidents
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a technician prescribing the loading <strong>of</strong> a manual rod<br />
followed by the unloading <strong>of</strong> another one. The technician<br />
did not wait until the moving control rod reached<br />
its bottom position and started the manipulation in the<br />
wrong order. He first extracted a manual rod instead <strong>of</strong><br />
first inserting the other.<br />
During the extraction <strong>of</strong> the manual rod the reactor<br />
became critical. The technician had his left foot<br />
projecting over the edge <strong>of</strong> the tank and resting on a<br />
grating that was about 50 mm above the reflector; his<br />
right foot and leg were somewhat behind him and<br />
partly shielded. He noticed a glow in the bottom <strong>of</strong> the<br />
reactor, immediately dropped the control rod, and left<br />
the room.<br />
11. Kurchatov Institute, 15 February 1971 77<br />
Experiments to evaluate the relative effectiveness <strong>of</strong><br />
iron and metallic beryllium as a reflector on a power<br />
reactor core were in progress at the critical experiment<br />
facility, SF-7. The core measured 1,200 mm high and<br />
1,000 mm in diameter and held 349 fuel rods. <strong>Criticality</strong><br />
was obtained by adding water to the core and<br />
immersing the fuel rods. The safety rods consisted <strong>of</strong> a<br />
lattice <strong>of</strong> boron carbide rods that could be inserted<br />
throughout the core to compensate for the operative<br />
reactivity margin. The boron carbide lattice did not<br />
cover the three outer rows <strong>of</strong> fuel rods. The fuel rods<br />
were enriched to about 20% 235 U (typical <strong>of</strong> icebreakers).<br />
The first stage <strong>of</strong> the experiment consisted <strong>of</strong> a core<br />
configuration in which the neutron flux was nonuniformly<br />
distributed along the core radius. Measurements<br />
showed that the completely water flooded core<br />
with the boron carbide safety rod lattice inserted was<br />
deeply subcritical (~10%), and the reactivity increased<br />
only slightly (+0.8%) after replacing the radial iron<br />
reflector with one <strong>of</strong> beryllium.<br />
The second stage <strong>of</strong> the experiment consisted <strong>of</strong> a<br />
core configuration in which the neutron flux was<br />
uniformly distributed along the core radius. One<br />
hundred forty–seven fuel rods with the maximum<br />
loading <strong>of</strong> burnable neutron absorber were inserted<br />
into the central part <strong>of</strong> the core that was heavily<br />
poisoned by a safety rod lattice. Two surrounding rows<br />
<strong>of</strong> rods (118 rods) containing less absorber, in this case<br />
a burnable poison, were then added. The outermost<br />
row (84 rods) did not contain burnable neutron<br />
absorber material.<br />
The energy release was 4.3 × 10 17 fissions and,<br />
apparently, the excursion was stopped by the falling<br />
manual rod, although the scram may have been<br />
speeded up by a combination <strong>of</strong> the Doppler effect and<br />
emptying <strong>of</strong> the vessel, which was automatically<br />
“provoked.” This is uncertain.<br />
No steam was created, no damage was done to the<br />
fuel, and there was no contamination. The technician<br />
received a severe radiation dose, primarily gamma–<br />
rays. Eight days later and after 300 measurements in a<br />
phantom, rough estimates were that the dose to his<br />
head was 300 to 400 rem, to his chest 500 rem, and to<br />
his left ankle 1,750 rem. At the end <strong>of</strong> his foot the dose<br />
approached 4,000 rem. Medical treatment <strong>of</strong> the<br />
patient was successful, except that the left foot had to<br />
be amputated.<br />
U(20)O 2 fuel rod, iron and beryllium reflected, assembly; multiple excursions; two serious exposures.<br />
The second stage <strong>of</strong> the experiment, according to<br />
the plan, began with the beryllium reflector in place<br />
because it was in place at the end <strong>of</strong> the first stage.<br />
However, criticality calculations for this core configuration<br />
were performed only for an iron reflector. Based<br />
on results <strong>of</strong> the comparison between beryllium and<br />
iron reflectors for the first configuration, the supervisor<br />
<strong>of</strong> the experimental team determined that substituting<br />
iron for beryllium would not result in any considerable<br />
increase in reactivity. Therefore, additional calculations<br />
were not performed.<br />
The core configuration with the beryllium reflector<br />
was assembled in the dry critical facility tank and left<br />
for the night. The next morning, the supervisor entered<br />
the facility control room (Figure 60) and without<br />
waiting for the arrival <strong>of</strong> the control console operator<br />
and the supervising physicist, switched on the pump,<br />
and began adding water to the critical assembly tank.<br />
The supervisor considered the system to be far from<br />
critical. The control equipment was switched on, but<br />
the neutron source had not been placed in the critical<br />
assembly, and the control rods were not actuated.<br />
A scientist arrived from Gorky who was training at<br />
the SF-7 experimental facility and was standing near<br />
the critical assembly tank discussing the experiment<br />
with the supervisor. Suddenly they saw a blue luminescence<br />
reflecting from the ceiling and heard a rapidly<br />
increasing signal from an audible neutron flux indicator.<br />
They thought that something had happened in<br />
another facility and ran from the critical assembly<br />
room. Other workers who were in the room also left.<br />
The manager <strong>of</strong> the facility was informed <strong>of</strong> the event.<br />
The manager and a dosimetry technician tried to enter<br />
99