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Regional Basic Professional Training Course in Korea

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Cladd<strong>in</strong>g failure<br />

❙ 181 ❙<br />

3. <strong>Basic</strong> Pr<strong>in</strong>ciples Of Nuclear Safety<br />

Failure of the cladd<strong>in</strong>g barrier can occur due to defects <strong>in</strong> end‐cap welds or <strong>in</strong> the<br />

cladd<strong>in</strong>g tube itself. Such failures are relatively rare compared to the number of fuel rods<br />

<strong>in</strong> a reactor. Other potential failure mechanisms <strong>in</strong>clude pellet‐cladd<strong>in</strong>g mechanical<br />

<strong>in</strong>teraction or high pressure due to fission gas release <strong>in</strong> transients, flow‐<strong>in</strong>duced or<br />

mechanical vibrations, or excessive cladd<strong>in</strong>g corrosion. Cladd<strong>in</strong>g failures can be detected<br />

promptly by detection of fission product radioactivity or delayed neutrons <strong>in</strong> the coolant.<br />

While plant technical specifications may allow operation with up to a specified fraction<br />

of defective fuel, prudent operat<strong>in</strong>g practice and ALARA pr<strong>in</strong>ciples dictate that failed<br />

fuel be removed at the earliest practical time to m<strong>in</strong>imize contam<strong>in</strong>ation of the primary<br />

coolant system with accompany<strong>in</strong>g radiation exposure to the plant operat<strong>in</strong>g and<br />

ma<strong>in</strong>tenance staff.<br />

3.5.2.3. The primary coolant system<br />

Description<br />

In a PWR, the primary coolant system pressure boundary consists of the reactor pressure<br />

vessel, the coolant pip<strong>in</strong>g, the steam generators, and ma<strong>in</strong> coolant pumps, along with<br />

some auxiliary systems <strong>in</strong>clud<strong>in</strong>g the pressurizer, chemical and volume control systems<br />

(CVCS), and parts of the emergency core cool<strong>in</strong>g and residual heat removal systems,<br />

depend<strong>in</strong>g on the design and operat<strong>in</strong>g details.<br />

The primary coolant system is <strong>in</strong>tended to be leak‐tight, except for controlled outflow, for<br />

example, through the ma<strong>in</strong> coolant pump seals, or the CVCS. Under normal conditions,<br />

the radioactive <strong>in</strong>ventory of the primary coolant system consists of radionuclides that<br />

have leaked from defective fuel, plus activated corrosion products. An important class of<br />

design basis accidents <strong>in</strong>volves loss of <strong>in</strong>tegrity of the pressure boundary. This class<br />

<strong>in</strong>cludes the large‐break loss‐of‐coolant accident (LBLOCA), and the small‐break<br />

loss‐of‐coolant accident (SBLOCA). So long as these accidents do not lead to core

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