Ageing management of safety-related concrete structures to provide improved bases for continuing the service of nuclear power plants

Author:

Naus D. J.,Oland C. B.,Arndt E. G.

Publisher

Springer Science and Business Media LLC

Subject

Mechanics of Materials,General Materials Science,Building and Construction,Civil and Structural Engineering,General Engineering

Reference29 articles.

1. ‘Regulatory options for nuclear power plant licence renewal’, NUREG-1317 (Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, US Nuclear Regulatory Commission, Washington, DC, 1988).

2. ‘LWR plant life extension’, EPRI NP-5002 (Electric Power Research Institute, Palo Alto, California, 1987).

3. ‘BWR pilot plant life extension study at the Monticello plant’, EPRI NP-5181M (Electric Power Research Institute, Palo Alto, California, 1987).

4. ‘PWR pilot plant life extension study at Surry Unit 1: Phase 1’, EPRI NP-5289P (Electric Power Research Institute, Palo Alto, California, 1987).

5. Naus, D. J., ‘Appendix B: Concrete material systems in nuclear safety-related structures-a review of factors related to their durability, degradation detection and evaluation, and remedial measures for areas of distress’, in ‘The Longevity of Nuclear Power Plant Systems’, edited by I. Spiewak and R. S. Livingston, EPRI NP-4208 (Electric Power Research Institute, Palo Alto, California, 1985).

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1. Mesoscale modelling and simulation of irradiation-induced expansion in concrete;International Journal of Mechanical Sciences;2024-08

2. Nondestructive evaluation techniques for thick concrete;Nondestructive Characterization and Monitoring of Advanced Materials, Aerospace, and Civil Infrastructure 2017;2017-04-19

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