Analysis of an advanced test reactor small-break loss-of-coolant accident with an engineered safety feature to automatically trip the primary coolantpumps
St. Polkinghorne et al., Analysis of an advanced test reactor small-break loss-of-coolant accident with an engineered safety feature to automatically trip the primary coolantpumps, NUCL TECH, 132(1), 2000, pp. 167-178
A new engineered safety feature that automatically trips the primary coolan
t pumps following a low-pressure reactor scram was recently installed in th
e Advanced Test Reactor (ATR). The purpose of this engineered safety featur
e is to prevent the ATR's surge tank, which contains compressed air, from e
mptying during a small-break loss-of-coolant accident (SBLOCA). If the surg
e tank were to empty, the air introduced into the primary coolant loop coul
d potentially cause the performance of the primary and/or emergency coolant
pumps to degrade, thereby reducing cove thermal margins. Safety analysis p
erformed with the RELAP5 thermal-hydraulic code and the SINDA thermal analy
zer shows that adequate thermal margins ave maintained during an SBLOCA wit
h the new engineered safety feature installed. The analysis also shows that
the surge tank will not empty during an,SBLOCA even if one of the primary
coolant pumps fails to trip.