steam generator (sg) meaning in Chinese

蒸汽产生器

Test investigation on sgtr of single tube break and three - tube break is carried out on hpitf of ciae to deeply understand the thermal - hydraulic behavior during pressurized - water - reactor ( pwr ) sgtr and to provide an integral data base for code assessment and development . the facility , a full height and 1 / 1000 - scale ( by volume ) of qinshan nuclear power plant , incorporates two identical loops with active pumps and steam generators ( sg ) . the initial steady state of the test basically simulated that of the reference plant operation
为了深入了解核电厂蒸汽发生器传热管破裂事故发生后的热工水力现象，以及对压水堆( pwr )核电厂系统分析程序进行分析和评价，在高压综合试验装置上开展了蒸汽发生器传热管破裂试验研究高压综合试验装置以秦山核电厂主回路系统为模拟对象，该装置为双环回路系统，容积比为1 ： 1000 ，高度比为1 ： 1 。