摘要
介绍了一个建立在两相漂移流和相边界可连续移动模型基础上的、可较为全面描述单相及两相流的传热和流动的程序CCM。该程序通过“修正的有限元方法”对控制体节点之间建立联系,保证模拟效果的同时,节省了计算时间。以CCM为基础的UTSG-3程序可较好地模拟U型管蒸汽发生器的稳态和瞬态过程,可得到更为广泛的应用。通过不同运行参数的扰动研究了大亚湾核电站蒸汽发生器动态响应过程,结果显示UTSG-3程序具有模拟U型管蒸汽发生器动态行为的能力。
A coolant channel module (CCM) is presented to simulate, in a very general way, the thermal-hydraulic behavior of single-and two-phase flow along a heated (or cooled) vertical, inclined or horizontal coolant channel. It is based on a drift-flux model with governing equations describing mass, momentum and energy balances for both the steady-state and transient flows in such a general channel. A special time-dependent quadratic polygon approximation method using a modified finite volume algorithm is employed to establish a connection between nodal boundaries and nodal-mean parameters. By using the code CCM, the U-tube steam generator simulation program UTSG-3 has been assembled, which simulates the transient behavior when steam generator operates under either normal or accident conditions. The transient responses of operation parameters of a steam generator similar to that of Daya Bay NPP are studied by means of different operation parameter perturbations. The results show that the UTSG-3 is capable of simulating the dynamic behavior of U-tube steam generator.
出处
《核科学与工程》
CSCD
北大核心
2006年第3期199-203,共5页
Nuclear Science and Engineering