ANALYSIS OF STEAM-GENERATOR LOSS-OF-FEEDWATER EXPERIMENTS WITH APROS AND RELAP5 MOD3.1 COMPUTER CODES/

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.