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Management of Commercially Generated Radioactive Waste - U.S. ...

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4.91<br />

which is postulated to result in large releases <strong>of</strong> radioactive material, may be substan-<br />

tially reduced with these additional transportation personnel. Thus, if a severe accident<br />

does occur, consequences may be partially mitigated compared to the severe accidents<br />

described here.<br />

Truck and rail transport <strong>of</strong> spent fuel are both expected to be used in the once-through<br />

fuel cycle. Descriptions <strong>of</strong> the systems considered in the analysis along with detailed<br />

accident descriptions are reported in DOE/ET-0028. Dose calculations for postulated acci-<br />

dents are reported in DOE/ET-0029. Accident frequency estimates cited in this section are<br />

based on an assumed 250 GWe nuclear industry.<br />

The impacts examined in DOE/ET-0028 and DOE/ET-0029 were developed assuming unpackaged<br />

short-cooled (6 months out <strong>of</strong> the reactor) spent fuel. These impacts are thus much more<br />

severe than those from accidents involving long-cooled fuel. They also do not take into<br />

account the mitigation <strong>of</strong> impact that is likely to result from the new escorting regulations.<br />

Similar accidents are also plausible for packaged spent fuel if transportation is<br />

required following packaging. However, since packaging provides an additional barrier to<br />

release <strong>of</strong> nuclides in transportation <strong>of</strong> spent fuel, the releases would be smaller and more<br />

infrequent than for unpackaged spent fuel. For this reason, specific accidents for packaged<br />

spent fuel transport are not discussed but can be assumed to cause lesser impact than<br />

unpackaged spent fuel transport.<br />

Six accidents for truck transport <strong>of</strong> spent fuel were analyzed: three minor, two moder-<br />

ate, and one severe. The minor accidents involved rollovers, collisions and the undetected<br />

leakage <strong>of</strong> coolant. Only coolant leakage was expected to release radioactive material and<br />

could result in a 70-yr accumulated dose to the maximum-exposed individual <strong>of</strong> 3 x 10 -6 rem<br />

at an expected frequency <strong>of</strong> approximately twice per year.<br />

The moderate accident giving the largest release <strong>of</strong> radioactive material is a fire<br />

that activated a pressure relief valve on the cask. A 70-yr accumulated dose <strong>of</strong><br />

8 x 10 -5 rem to the maximum-exposed individual would occur at an estimated frequency <strong>of</strong><br />

about once every 50 years.<br />

The severe accident culminating in a long-lasting fire results in a 70-yr accumulated<br />

dose to the maximum-exposed individual <strong>of</strong> 10 rem. The estimated frequency for this accident<br />

is about once every 50,000 years.<br />

Eight accidents for rail transport <strong>of</strong> spent fuel were analyzed: three minor, three<br />

moderate and two severe. Two minor accidents involved derailments and 30-minute fires; no<br />

release occurred. The third minor accident involved undetected leakage <strong>of</strong> cask coolant.<br />

This accident could occur up to twice per year and result in a 70-yr accumulated dose <strong>of</strong><br />

2 x 10 -5 rem to the maximum-exposed individual.<br />

The moderate accidents involved cask impacts, fire-induced cask venting, and failures<br />

in the mechanical cooling system as a result <strong>of</strong> accident forces. The cooling system fail-<br />

ure is estimated to occur once every 50 years and results in a 70-yr accumulated dose <strong>of</strong><br />

8 x 10 -5 rem to the maximum-exposed individual.

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