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A Review of Criticality Accidents A Review of Criticality Accidents

A Review of Criticality Accidents A Review of Criticality Accidents

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235 U Spherical Critical Mass (kg)<br />

100<br />

10<br />

1<br />

9<br />

0.8<br />

20 100 500 1000 2000<br />

Figure 38. Critical masses <strong>of</strong> water-reflected spheres <strong>of</strong> hydrogen-moderated U(93), U(30.3), U(5.00), U(3.00), and<br />

U(2.00). The accidents are shown by numbered circles.<br />

Fission Yields<br />

Table 10 lists the estimated fission energy releases<br />

for the 22 accidents. An attempt has been made to<br />

categorize the spike yield in this edition in a manner<br />

consistent with the prior two editions <strong>of</strong> this report and<br />

definitions in the appendix. These definitions are<br />

repeated here for convenience.<br />

spike (in a prompt power excursion): The initial<br />

power pulse <strong>of</strong> a prompt power excursion, limited by<br />

the shutdown mechanism. See excursion, prompt<br />

power.<br />

excursion, prompt power: A nuclear excursion as<br />

the result <strong>of</strong> a prompt critical configuration <strong>of</strong> fissile<br />

material. In general, a sharp power spike followed by a<br />

plateau that may be interrupted by smaller spikes.<br />

From solution excursion experimental data, such as<br />

many <strong>of</strong> the CRAC4 and SILENE3 experiments, it is<br />

apparent that there is a smooth transition from excursions<br />

in which the maximum reactivity did not reach<br />

prompt critical to those in which it slightly exceeded<br />

prompt critical. There is no significant distinction<br />

H/ 235 U Atomic Ratio<br />

U(2)F –Paraffin<br />

2<br />

U(3)F –Paraffin<br />

2<br />

U(5)O2F2 Solution<br />

U(30.3)O F Solution<br />

2 2<br />

U(93)O F Solution<br />

2 2<br />

Calculated UO F –Water<br />

2 2<br />

Calculated UF –Paraffin<br />

4<br />

22<br />

15<br />

between the power histories <strong>of</strong> two excursions, one<br />

having a maximum reactivity <strong>of</strong> $0.90 and the other<br />

having a maximum reactivity <strong>of</strong> $1.10. They both<br />

exhibit an initial spike followed by less energetic,<br />

recurring spikes at approximately 10 to 20 second<br />

intervals, eventually leading to a quasi–plateau. Only<br />

when the maximum reactivity attained is about $0.50<br />

or less is the traditional spike not present.<br />

Another result <strong>of</strong> the CRAC 4 and SILENE 3 experiments<br />

that can be compared to the accident yields<br />

listed in Table 10 is the specific yield <strong>of</strong> the first<br />

excursion, the spike. For experiments with a maximum<br />

reactivity <strong>of</strong> about $0.50 or more, the specific yield <strong>of</strong><br />

the spike was always about 1.0 × 10 15 fissions per liter<br />

except for very fast excursions, those that achieved<br />

inverse periods much greater than 100 s –1 . For these<br />

very fast excursions, specific yields up to several times<br />

10 15 fissions per liter were measured. The accidents for<br />

which a spike yield is given in Table 10 are consistent<br />

with the specific yields <strong>of</strong> the CRAC 4 and SILENE 3<br />

data in that none exceeded a few times 10 15 fissions<br />

per liter. However, there are three reported spike yields<br />

61

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