铅铋堆蒸汽发生器传热管破裂事故三维程序开发及验证

Development and Verification of 3D Code for Steam Generator Tube Rupture Accident of LBE-cooled Reactor

蒸汽发生器(SG)传热管破裂事故(SGTR)是铅铋堆设计必须重点考虑的安全问题之一。针对铅铋堆SGTR,为解决其复杂结构环境中压力波的三维传播与蒸汽的三维迁移难题,基于多相流欧拉流体动力学理论,开展了“铅铋-水”相互作用三维数值模型与算法研究,研制了专用程序,并采用实验对比和程序对比技术手段进行了程序验证,验证结果符合较好。研究结果表明:对于描述铅铋堆SGTR过程中“铅铋-水”相互作用行为,本文采用的相关数值理论与模型具有较好的适用性;对于研究复杂结构环境下铅铋堆SGTR的三维演化现象,包括压力波传播、蒸汽迁移,本文所开发的三维程序具有重要的潜在应用价值。本文研究成果有望为我国铅铋堆SGTR分析提供有力支撑。

Steam Generator Tube Rupture(SGTR)accident is one of the significant safety problems that must be considered in the design of Lead-Bismuth-Eutectic(LBE)cooled reactor.With respect to the SGTR in LBE-cooled reactor,and to cope with the challenges of 3D propagation of pressure waves and 3D migration of water steam under the complex geometric structures,the three-dimensional numerical model and algorithm of the interaction between LBE and water were studied based on the Euler hydrodynamic theory of multiphase flow,and a special code was developed.The code was verified by means of experimental comparison and code-to-code comparison,and the verification results were in good agreement.It is demonstrated that the numerical theories and models used in this paper are suitable for describing the"LBE-water"interaction during SGTR accidents in LBE-cooled reactors.And the 3D code developed in this paper has important potential application values in coping with the 3D evolution processes of SGTR accidents in LBE-cooled reactors under the complex geometric structures,including the pressure wave propagation and steam migration.The research achievements in this paper are expected to provide strong supports for the SGTR accident analyses of LBE-cooled reactors in China.