H. Asaka et al., CORE LIQUID-LEVEL RESPONSES DUE TO SECONDARY-SIDE DEPRESSURIZATION DURING PWR SMALL BREAK LOCA, Journal of Nuclear Science and Technology, 35(2), 1998, pp. 113-119
The effects of the rate of intentional secondary-side depressurization
and of the break area on the core liquid level behavior during a PWR
small-break LOCA with total failure of the high pressure injection (HP
I) systems were studied using experimental data from the Large Scale T
est Facility (LSTF) and using analysis results obtained with the REFLA
/TRAC code. The LSTF is a 1/48 volumetrically scaled full-height integ
ral model of a Westinghouse-type PWR. The code reproduced the thermal-
hydraulic responses observed in the experiment for important parameter
s such as the primary and secondary-side pressures and core liquid lev
el. The sensitivity of the core minimum liquid level to the depressuri
zation rate and break area was studied by using the code assessed abov
e. It was found that the core liquid level took a local minimum value
for a given break area as a function of secondary-side depressurizatio
n rate. The core temperature was kept below about 1,000 K when the sec
ondary depressurization rate was greater than -200 K/h in the saturati
on temperature for break areas smaller than 2.5%.