Test Investigation On Steam Generator U-tube Rupture Of Different Break Size

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. The break assembly was connected to the secondary system at one location. The break was assumed to be a single tube double-ended and three-tube double-ended shear break. The diameter of the break orifice is 0.876mm and 1.518mm respectively. The characteristic responses of main thermal-hydraulic parameters, such as primary pressure, secondary pressure, break flow rate, pressurizer level, secondary side level of steam generator and so on, were presented in this thesis.Post-test analyses for this test (a single tube double-ended break) were performed with RELAP5/MOD2 code. The analysis showed that the results were in good agreement with the test data.