E. Virtanen et al., ANALYSIS OF STEAM-GENERATOR LOSS-OF-FEEDWATER EXPERIMENTS WITH APROS AND RELAP5 MOD3.1 COMPUTER CODES/, Nuclear Engineering and Design, 177(1-3), 1997, pp. 147-153
Three experiments were conducted to study the behaviour of the new hor
izontal steam generator construction of the PACTEL test facility. In t
he experiments the secondary side coolant level was reduced stepwise.
The experiments were calculated with two computer codes RELAPS/MOD3.1
and APROS version 2.11. A similar nodalization scheme was used for bot
h codes so that the results may be compared. Only the steam generator
was modeled and the rest of the facility was given as a boundary condi
tion. The results show that both codes calculate well the behaviour of
the primary side of the steam generator. On the secondary side both c
odes calculate lower steam temperatures in the upper part of the heat
exchange tube bundle than was measured in the experiments. (C) 1997 El
sevier Science S.A.