Deterministic structural and fractural mechanics analyses of reactor pressure vessel for pressurized thermal shock

Structural Engineering and Mechanics

Volumn 8, Issue 1, 1999, Pages 103-118

  Jhung, M J ^a   Park, Y W ^a  

^a Korea Institute of Nuclear Safety (KINS)   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

CRACK INITIATION; FRACTURE MECHANICS; FRACTURE TOUGHNESS; PRESSURE VESSELS; STRESS CONCENTRATION; STRESS INTENSITY FACTORS;

NIL DUCTILITY TRANSITION TEMPERATURE; PRESSURIZED THERMAL SHOCK; REACTOR VESSEL;

STRUCTURAL ANALYSIS;

EID: 0033165499     PISSN: 12254568     EISSN: None     Source Type: Journal    
DOI: 10.12989/sem.1999.8.1.103     Document Type: Article

References (14)

1. ASME (1995a), "Rules for construction of nuclear power plant components", ASME Boiler and Pressure Vessel Code, Section III.
2. ASME (1995b), "Rules for inservice inspection of nuclear power plant components", ASME Boiler and Pressure Vessel Code, Section XI.
3. Curry, D.A. (1983), "A model for predicting the influence of warm pre-stressing and strain aging on the cleavage fracture toughness of ferritic steels", International Journal of Fracture, 22, 145-159.
4. Harvey, J.F. (1960), Theory and Design of Modern Pressure Vessels, 2nd ed., Van Nostrand Reinhold Co., New Jersey.
5. McGowan, J.J. (1979), "Application of warm prestressing effects to fracture mechanics analyses of nuclear reactor vessels during severe thermal shock", Nuclear Engineering and Design, 51, 431-444.
6. Mishima, Y., et al. (1994), "PTS integrity study in Japan", International Journal of Pressure Vessels and Piping, 58, 91-101.
7. Myers, M.N. (1971), Analytical Method in Conduction Heat Transfer, McGraw-Hill, New York.
8. Ozisik, M.N. (1980), Heat Conduction, John Wiley & Sons.
9. Pennell, W.E. (1993), "Heavy-section steel technology program overview", Nuclear Engineering and Design, 142, 117-135.
10. Sievers, J. (1996), "Reactor pressure vessel pressurized thermal shock international comparative assessment study", OECD/NEA PWG-3, December 23.
11. Sievers, J. (1997), "The interim workshop on RPV PTS ICAS", OECD/NEA PWG-3, June 2.
12. Stahlkopf, K.E. (1984), "Pressure vessel integrity under pressurized thermal shock conditions", Nuclear Engineering and Design, 80, 171-180.
13. Timoshenko, S.P. and Goodier, J.M. (1970), Theory of Elasticity, 3rd ed., McGraw-Hill, New York.
14. USNRC (1988), "Radiation embrittlement of reactor vessel materials", Regulatory Guide 1.99, Rev.2, US Nuclear Regulatory Commission, May.