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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 />

0611 and NUREG‐0635 are applied for the West<strong>in</strong>ghouse Plants and Combustion<br />

Eng<strong>in</strong>eer<strong>in</strong>g (CE) Plants, respectively. They <strong>in</strong>cludes [3]:<br />

(1) Demonstrate the acceptability of the condensation heat transfer correlation used <strong>in</strong><br />

the steam generator.<br />

(2) Address the affects of noncondensible gases on the condensation heat transfer.<br />

(3) Justify the conservatism of model<strong>in</strong>g ECC mix<strong>in</strong>g as an equilibrium process.<br />

(4) Validate the computer program with LOFT <strong>in</strong>tegral experiments L3‐1 and L3‐6,<br />

and Semiscale experiment S‐UT‐08.<br />

(5) Validate the steam generator model.<br />

(6) Validate the core heat transfer and the liquid level model.<br />

(7) Confirm adequate account<strong>in</strong>g of the stored energy(heat) with<strong>in</strong> the primary system<br />

metal structures.<br />

(8) Validate the acceptability of apply<strong>in</strong>g a 1.0 discharge coefficient on both th-<br />

e subcooled and saturated flow models.<br />

8.8.2.2 SBLOCA Analysis Methods and Results<br />

The models or methodologies which were approved and have been used for plant<br />

calculation up to now <strong>in</strong> <strong>Korea</strong> Standard Nuclear Power Plants (KSNP) <strong>in</strong>clude the CE<br />

methodology based on CEFLASH code and the West<strong>in</strong>ghouse methodology us<strong>in</strong>g<br />

NOTRUMP code<br />

8.8.2.2.1 CE Methodology [4]<br />

It composed of calculations us<strong>in</strong>g four codes as follows:<br />

(1) Calculation of thermal‐hydraulic response of RCS from the beg<strong>in</strong>n<strong>in</strong>g of SBLOCA<br />

❙ 538 ❙

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