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Regional Basic Professional Training Course in Korea

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8.5.3. Decrease <strong>in</strong> Reactor Coolant Flow Rate<br />

❙ 491 ❙<br />

8-A. Determ<strong>in</strong>istic Accident Analysis (Non‐LOCA)<br />

For a PWR, the <strong>in</strong>itiat<strong>in</strong>g events that can result <strong>in</strong> decrease <strong>in</strong> reactor coolant flow rate are<br />

as follows:<br />

• Total loss of reactor coolant flow;<br />

• S<strong>in</strong>gle reactor coolant pump (RCP) rotor seizure with loss of offsite power;<br />

• Reactor coolant pump shaft break with loss of offsite power.<br />

Among the events listed above, first event is an AOO and the rema<strong>in</strong><strong>in</strong>g two events are<br />

accidents.<br />

An RCP coastdown due to an <strong>in</strong>terruption of the power supply or failure of the control<br />

system is the most typical case for a reduction of primary coolant flow. Reduction of the<br />

RCS flow leads to an imbalance between heat produced by the fuel and heat removed<br />

from the core, potentially threaten<strong>in</strong>g the marg<strong>in</strong>‐to‐DNB. Thermal imbalance also leads<br />

to an overall pressure–temperature transient, typically result<strong>in</strong>g <strong>in</strong> a short term<br />

pressurization of both the primary and the secondary circuit.<br />

The possible cause of the RCP rotor seizure or shaft break is a mechanical damage. The<br />

event itself is characterized by a very sharp reduction of the flow <strong>in</strong> the correspond<strong>in</strong>g<br />

loop, typically with<strong>in</strong> a time shorter than one second. In the RCP rotor seizure case, it is<br />

assumed that the support components are designed to withstand transient mechanical<br />

loads without RCS pip<strong>in</strong>g failure.<br />

Figure 8‐4 shows one example of predicted DNBR trends versus time for a S<strong>in</strong>gle RCP<br />

Rotor Seizure with Loss of Offsite Power.

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