Serviceability design load factors and reliability assessments for reinforced concrete containment structures

Nuclear Engineering and Design

Volumn 179, Issue 2, 1998, Pages 201-208

  Han, Bong Koo ^a   Ang, Afredo H S ^b  

^a Seoul National University of Science and Technology   (South Korea)

^b University of California at Irvine   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CODES (STANDARDS); CONCRETE CONSTRUCTION; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; PROBABILITY; RANDOM PROCESSES; REINFORCED CONCRETE; RELIABILITY; SAFETY FACTOR; SERVICE LIFE; STRUCTURAL DESIGN; STRUCTURAL LOADS;

SERVICEABILITY DESIGN LOAD FACTORS;

CONTAINMENT VESSELS;

EID: 0031999104     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(97)00265-3     Document Type: Article

References (19)

1. ACI Manual Concrete Practice, 1988. Part 3, pp. 224R-18.
2. ACI-ASME Joint Technical Committee, 1980. Code for concrete reactor vessels and containments. ASME Boiler and Pressure Vessel Code Section III - Division 2, Am. Soc. Mech. Eng., New York.
3. Ang, A.H.-S., Tang, W.H., 1984. Probability concepts in engineering planning and design. Decision, Risk and Reliability, vol. 2. John Wiley, New York.
4. Ang, A.H.-S., 1991. Recent PRA developments for nuclear structural systems. Proc. of SMiRT 11, Post-Conference Seminar No. 8.
5. Cave, L., Kastenberg, W.E., 1991. On the application of probabilistic risk assessment to reactors with inherently safe features. J. Nucl. Eng. Des. 128, 339-347.
6. Clough, R.W., Penzien, J., 1975. Dynamics of Structures. McGraw-Hill, New York.
7. Ellingwood, B., Hwang, H., 1985. Probabilistic descriptions of resistance of safety-related structures in nuclear plants. J. Nucl. Eng. Des. 88, 169-178.
8. Ellingwood, B., Galambo, T.V., MacGregor, J.C., Cornell, C.A., 1980. Development of a probability-based load criterion for American National Standard A58. National Bureau of Standard SP-577, Washington, DC.
9. Han, B.K., Cho, H.N., Chang, S.P., 1989. A practical reliability-based design code calibration for concrete containment structures. Proceedings of the tenth SMiRT Conference, Anaheim, LA, Paper M, pp. 85-90.
10. Han, B.K., Cho, H.N., Chang, S.P., 1991. Reliability-based design code calibration for concrete containment structures. J. Nucl. Eng. Des. 128 (2), 7, 207-216.
11. Kanai, K., 1957. Semi-empirical formula for the seismic characteristics of the ground. Bulletin of the Earthquake Research Institute, University of Tokyo, vol. 35, pp. 309-325.
12. Kuroda, T., Ebine, T., Sato, S., Kato, M., 1993. Recent advances in concrete containment vessels in Japan. J. Nucl. Eng. Des. 140, 3-18.
13. Nawy, E.G., 1972. Crack control through reinforcement distribution in two-way acting slabs and plates. ACI J. Proc. 69 (4), 217-219.
14. Schuëller, G.I., 1984. Impact of probability risk assessment on containment. J. Nucl. Eng. Des. 80, 203-216.
15. Schuëller, G.I., 1989. Reliability of nuclear structures. J. Nucl. Eng. Des. 114, 235-245.
16. Shinozuka, M., Hwang, H., Reich, M., 1983. Reliability assessment of reinforced concrete containment structures. BNL-NUREG-51661.
17. Suzuki, T., Takiguchi, K., Hotta, H., 1992. Leakage of gas through concrete cracks. J. Nucl. Eng. Des. 133, 121-130.
18. Tajimi, H., 1960. A statistical method of determining the maximum response of the building structure during an earthquake. Proceedings of the 2nd World Conference on Earthquake Engineering, Tokyo and Kyoto, vol. 2, pp. 781-796.
19. Yu, C.S., 1987. Seismic risk and design input criteria for nuclear power structures in Korea. Proceedings of the US-Korea Joint Seminar/Workshop on Critical Engineering System, Seoul.