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Chernobyl Nuclear Accident Congressional Hearings Transcript

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272<br />

QUESTION 10. (Continued) - 8 -<br />

radioactivity release magnitudes similar to those in WASH-1400 PWR<br />

3 or BWR 3 release categories. These release categories contain<br />

many accident scenarios, including small break loss of coolant<br />

with failure of the containment sprays, interfacing systems loss<br />

of coolant (i.e'. , accidents involving overpressurization of low<br />

pressure piping that is outside of the containment but is<br />

connected to the high pressure primary cooling piping such that<br />

the loss of coolant occurs outside of the containment rather than<br />

the design basis loss of coolant inside containment), anticipated<br />

transients without scram, station blackout, and loss of coolant<br />

accidents with failure of emergency core cooling injection.<br />

The specific release category that results from these scenarios is<br />

dependent on core meltdown phenomena and containment response<br />

thereto. While much progress has been made in understanding these<br />

since WASH-1400 was published in 1975, there remain very<br />

substantial uncertainties in evaluating them. For example, during<br />

a core meltdown, theoretical source term calculations include<br />

models for plating out of significant quantities of fission<br />

products within the primary system. However, the models do not<br />

evaluate or poorly evaluate the effects of the heating of the<br />

primary system by the plated-out fission products to determine<br />

whether this phenomenon alters the sequence of events and the<br />

release category. Steam explosions and their effects on<br />

containment and resuspension of fission products are still in<br />

dispute. These are just two examples of the mary uncertainties

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