Research Article

The R&D of HTR-STAC Program Package: Source Term Analysis Codes for Pebble-Bed High-Temperature Gas-Cooled Reactor

Table 4

The comparison of experiment result, theoretical calculation, and HTR-STAC result of several typical nuclides in primary circle coolant of HTR-10.

NuclideExperiment (Bq/L) [14]Theoretical calculation (Bq/L) [14]LOOP (Bq/L)

Kr-85m3.90E+032.30E+044.58E+03
Kr-871.20E+045.30E+048.46E+03
Kr-881.20E+045.40E+041.33E+04
Xe-1331.40E+033.70E+041.12E+04
Xe-1352.10E+044.20E+047.37E+03
Xe-135m1.90E+042.10E+042.28E+03