Leak-Before-Break assessment of a welded piping based on 3D finite element method
Tài liệu tham khảo
Abaqus, 2012
Bilby, 1986
Bourga, B., 2016. The Effect of Crack Shape Idealization on Leak-Before-Break Assessment. In: Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Vancouver, Canada.
Chattopadhyay, 1992
Chen, 2014, Structural integrity assessment of the reactor pressure vessel under the pressurized thermal shock loading, Nucl. Eng. Des., 272, 84, 10.1016/j.nucengdes.2014.01.021
Chen, 2016, Fracture mechanics assessment of thermal aged nuclear piping based on the leak-before-break concept, Nucl. Eng. Des., 301, 333, 10.1016/j.nucengdes.2016.03.025
Dodds, 1991, A framework to correlate a/W ratio effects on elastic-plastic fracture toughness (Jc), Int. J. Fract., 48, 1, 10.1007/BF00012499
Electric Power Research Institute, 1989
Electric Power Research Institute, 1997
Electric Power Research Institute, 2006
Electric Power Research Institute, 2009
Ghadiali, 1996
Gong, 2013, Leak-before-break analysis of a dissimilar metal welded joint for connecting pipe-nozzle in nuclear power plants, Nucl. Eng. Des., 255, 1, 10.1016/j.nucengdes.2012.09.030
International Atomic Energy Agency, 2010
Julisch, 1995, Exclusion of rupture for welded piping of power stations by component tests and failure approaches, Nucl. Eng. Des., 158, 191, 10.1016/0029-5493(95)01028-G
Kanninen, 1985, Elastic-plastic fracture mechanics
Kim, 2016, Effective applied moment in circumferential through-wall cracked pipes for leak-before-break evaluation considering pipe restraint effects, Nucl. Eng. Des., 301, 175, 10.1016/j.nucengdes.2016.02.028
Li, 2013, Probabilistic fracture mechanics analysis of thermally aged nuclear piping in a pressurized water reactor, Nucl. Eng. Des., 265, 611, 10.1016/j.nucengdes.2013.06.034
Lv, 2014, Effect of thermal aging on the leak-before-break analysis of nuclear primary pipes, Nucl. Eng. Des., 280, 493, 10.1016/j.nucengdes.2014.10.012
Ma, L. W., Zhang, X.T. Comparison of Leak-Before-Break Assessment of Main Loop Piping Lines Fabricated of Different Materials. In: Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Vancouver, Canada.
Marie, 2007, French RSE-M and RCC-MR code appendices for flaw analysis: presentation of the fracture parameters calculation-Part III: cracked pipes, Int. J. Press. Vessels Pip., 84, 614, 10.1016/j.ijpvp.2007.05.005
Norris, 1987
Paul, 2010
Qian, 2015, Investigation on constraint effect of a reactor pressure vessel subjected to pressurized thermal shocks, J. Pressure Vessel Technol., 137, 1, 10.1115/1.4030299
Qian, 2010, Effect of residual stresses on the linear-elastic KI–T field for circumferential surface flaws in pipes, Eng. Fract. Mech., 77, 2682, 10.1016/j.engfracmech.2010.06.014
Qian, 2013, Probabilistic leak-before-break analysis with correlated input parameters, Nucl. Eng. Des., 254, 266, 10.1016/j.nucengdes.2012.10.005
Rahman, 1996, Effects of off-centered cracks and restraint of induced bending caused by pressure on the crack-opening-area analysis of pipes, Nucl. Eng. Des., 67, 155
RCC-M., 2010
Scott, 2005
Stadtmuller, 1997, Leak-before-break behavior of austenitic and ferritic pipes containing circumferential defects, Nucl. Eng. Des., 174, 335, 10.1016/S0029-5493(97)00130-1
Thorwald, G., Wang, B., 2016. Leak-Before-Break Assessment of A Cracked Reactor Vessel Nozzle Using 3D Crack Meshes. In: Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Vancouver, Canada.
U. S. Nuclear Regulatory Commission, 1996
U. S. Nuclear Regulatory Commission, 2002
U. S. Nuclear Regulatory Commission, 2007
U.S. Nuclear Regulatory Commission, 1984
Williams, 1957, On the stress distribution at the base of a stationary crack, ASME J. Appl. Mech., 109, 10.1115/1.4011454
Xu, 1995, Two-phase critical discharge of initially saturated or subcooled water flowing in sharp-edged tubes at high pressure, J. Therm. Sci., 4, 193, 10.1007/BF02650828