Fracture mechanics analysis and evaluation for the RPV of the Chinese Qinshan 300 MW NPP under PTS

Fracture analysis of the set-in nozzle of a PWR reactor pressure vessel – Part 1: Determination of critical crack

“…In 2000, He and Isozaki [12], performed fracture mechanics analysis of the beltline region of the RPV of a Chinese pressurized water reactor. The authors conducted the fracture analysis under small-break loss of coolant accident, large-break loss of coolant accident and Rancho-Seco transients.…”

Stress intensity factors of corner cracks at set-in nozzle–cylinder intersection of a PWR reactor pressure vessel

“…The internal pressure equals to 17.16 MPa (P int = 17.16 MPa) is applied to the RPV. This is the design pressure [12] of the RPV. 6.…”

“…The behavior of the material at T = 350 °C is used. This is the design temperature [12] of the RPV. Fig.…”

“…Fig. 3 True stress-strain characteristics [12] 7. The bending loads caused by the support pads on the nozzles have been taken into account.…”

Parametric design of scaled-down pressurised thermal shock test specimens using inelastic analysis

“…In general, the most accurate method of analysis is to use elastic-plastic Finite Element Analysis (FEA) of the cracked component, and calculate the J-integral as a function of position on the crack tip line [3]. Many examples of crackedbody FEA applied to PTS events in RPVs exist, including examples of both elastic analysis [15] and inelastic analysis [16], [17]. The elastic-plastic cracked-body FEA approach is used in the current study.…”