Probabilistic fracture analysis for boiling water reactor vessels considering seismic loads during decommissioning transition period

Author:

Chou Hsoung-Wei,Chang Ching-Hsin

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference34 articles.

1. BWRVIP, 1995. BWR reactor pressure vessel shell weld inspection recommendations (BWRVIP-05). BWR Vessel and Internals Project, EPRI TR-105697, Boiling Water Reactor Vessel & Internals Project and Electric Power Research Institute, Palo Alto, California, USA.

2. Chen, J.T., Chokshi, N.C., Kenneally, R.M., Kelly, G.B., Beckner, W.D., McCracken, C., Murphy, A.J., Reiter, L., Jeng, D., 1991. Procedural and submittal guidance for the individual plant examination of external events (IPEEE) for severe accident vulnerabilities. NUREG-1407, U.S. Nuclear Regulatory Commission, USA.

3. Cheverton, R.D., Ball, D.G., 1984. A deterministic and probabilistic fracture-mechanics code for applications to pressure vessels. NUREG/CR-3618.

4. Dynamics of structures-theory and application to earthquake engineering;Chopra,2001

5. Effects of fracture toughness curves of ASME Section XI–Appendix G on a reactor pressure vessel under pressure–temperature limitoperation;Chou;Nucl. Eng. Des.,2014

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