Mh. Chun et al., DEVELOPMENT OF A COMPUTER CODE TO ESTIMATE THE FUEL-ROD FAILURE USINGPRIMARY COOLANT ACTIVITIES OF OPERATING PWRS, Annals of nuclear energy, 25(10), 1998, pp. 753-763
A Windows computer code entitled as ''CAAP (Coolant Activity Analysis
Program)'' has been developed to evaluate the number,;he degree of fai
lures, and the location of failed fuel rods using primary coolant radi
oactivity data obtained from operating PWRS. New models are developed
and incorporated into the CAAP program to improve some of the drawback
s of existing computer codes. The iodine and noble gas activities obta
ined by grab sampling and that obtained from the primary coolant radio
activity monitoring system can be used to estimate fuel rod failures w
ith CAAP. For an on-line evaluation of the number of failed fuel rods
and the degree of failures, CAAP has been combined with the primary co
olant radioactivity monitoring system at Kori 3 & 4 operating nuclear
power plants. The validity of the computational models of CAAP has bee
n examined using nuclear power plant data collected. For 29 cycles of
PWRs for which ultrasonic inspections were performed at the end of fue
l cycles, the number of failed fuel rods has been estimated with CAAP
and compared with the ultrasonic inspection results. The results show
that CAAP gives a better agreement with the ultrasonic test data than
existing models. In addition, CAAP calculations performed to estimate
the region and the burnup of the failed fuel rods for 2 cycles, whose
locations of failed fuel rods were known, show that CAAP can predict b
oth the region and the burnup of the failed fuel rods accurately. (C)
1998 Elsevier Science Ltd.