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Regional Basic Professional Training Course in Korea

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<strong>Regional</strong> <strong>Basic</strong> <strong>Professional</strong> <strong>Tra<strong>in</strong><strong>in</strong>g</strong> <strong>Course</strong> (BPTC) on Nuclear Safety<br />

quantity of fission products towards the conta<strong>in</strong>ment. The phase of progressive <strong>in</strong>‐vessel<br />

heat<strong>in</strong>g‐up and melt<strong>in</strong>g establishes the <strong>in</strong>itial conditions for the assessment of the thermal<br />

and mechanical loads that may ultimately threaten the <strong>in</strong>tegrity of the conta<strong>in</strong>ment.<br />

The ex‐vessel progression of severe accidents is affected by the mode and tim<strong>in</strong>g of the<br />

failure of the reactor pressure vessel, the pressure <strong>in</strong> the reactor coolant system at vessel<br />

failure, the composition, amount and nature of the molten core debris expelled, the type<br />

of concrete used <strong>in</strong> the construction of the conta<strong>in</strong>ment, and the availability of water <strong>in</strong><br />

the reactor cavity. Some highly energetic phenomena may be caused by severe accidents.<br />

Such phenomena could cause the ultimate load bear<strong>in</strong>g capacity of conta<strong>in</strong>ments<br />

constructed by means of exist<strong>in</strong>g technologies to be exceeded, and consequently lead to a<br />

large early release of radionuclides to the environment.[3]<br />

Therefore, when the core is degraded, it is essential that conta<strong>in</strong>ment leaktightness is<br />

ma<strong>in</strong>ta<strong>in</strong>ed for as long as possible. This is the purpose of the Severe Accident<br />

Management Guidel<strong>in</strong>e (SAMG) <strong>in</strong> US or some of the U procedures <strong>in</strong> France. If the<br />

accident cannot be controlled, failure of conta<strong>in</strong>ment is unavoidable <strong>in</strong> the long term.<br />

The different sequence stages for a severe accident are summarized <strong>in</strong> Fig. 16.4.3.<br />

Follow<strong>in</strong>g <strong>in</strong>itiators (breaks, equipment failure, etc) accumulated as a result of safety<br />

system failures, four ma<strong>in</strong> stages can be dist<strong>in</strong>guished <strong>in</strong> the development of the accident,<br />

if it is not controlled [6]:<br />

1 st stage: reactor coolant system dra<strong>in</strong><strong>in</strong>g;<br />

2 nd stage: core water depletion and degradation;<br />

3 rd stage: vessel melt through;<br />

4 th stage: basemat erosion by the corium.<br />

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