1 |
ASME, ASME Boiler and Pressure Vessel Code, Section III, Appendix I Design Stress Intensity Values, Allowable Stresses, Material Properties, and Design Fatigue Curves, The American Society of Mechanical Engineers (2004)
|
2 |
Jhung, M.J., Kang, D.G., and Jo, J.C., 'Coupled Thermal Hydraulic and Stress Analysis of Pipe with Two Bends,' Transactions of the Korean Society of Pressure Vessels and Piping, Vol.3, No.2, pp.65-70 (2007)
|
3 |
USNRC, Pressurizer Surge Line Thermal Stratification, Bulletin No. 88-11, U.S. Nuclear Regulatory Commission, Washington, DC (1988)
|
4 |
USNRC, 'Effect of LWR Coolant Environments on Fatigue Life of Reactor Materials,' NUREG/CR-6909, U.S. Nuclear Regulatory Commission, Washington, DC (2007)
|
5 |
Grimes, R.G., Lewis, J.G., and Simon, H.D., 'A Shifted Block Lanczos Algorithm for Solving Sparse Symmetric Generalized Eigenproblems,' SIAM Journal on Matrix Analysis and Applications, Vol.15, No.1, pp.228-272 (1994)
DOI
ScienceOn
|
6 |
USNRC, Thermal Stresses in Piping Connected to Reactor Coolant Systems, Bulletin No. 88-08, U.S. Nuclear Regulatory Commission, Washington, DC (1988)
|
7 |
NEA, Thermal Cycling in LWR Components in OECDNEA Member Countries, NEA/CSNI/R(2005)8, NEA CSNI, CSNI Integrity and Ageing Working Group, Organization for Economic Co-operation and Development (2005)
|
8 |
ANSYS, ANSYS Structural Analysis Guide, ANSYS, Inc., Houston (2007)
|
9 |
USNRC, 'Guidelines for evaluating fatigue analysis incorporating the life reduction of metal components due to the effects of the light-water reactor environment for new reactors,' Regulatory Guide 1.207, U.S. Nuclear Regulatory Commission, Washington, DC (2007)
|