Serviceability design load factors and reliability assessments for reinforced concrete containment structures-Reference-Cited by-同舟云学术

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

Published:1998-02 Issue:2 Volume:179 Page:201-208
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Han Bong Koo,Ang Afredo H.-S

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference19 articles.

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.

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