Adaptive fuzzy system for degradation study in nuclear power plants' passive components

Author:

Guimarães Antônio César Ferreira,Cabral Denise Cunha,Lapa Celso Marcelo Franklin

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference16 articles.

1. ACI 349, 2001. Code Requirements for Nuclear Safety Related Concrete Structures. American Concrete Institute, Farmington Hills, MI.

2. ACI 318-99, 1999. Building Code Requirements for Reinforced Concrete. American Concrete Institute, Farmington Hills, MI.

3. ANSYS, Finite Element Computer Code, ANSYS Ver. 5.4. ANSYS, Inc., Canonsburg, PA.

4. Degradation assessment of structures and passive components at nuclear power plants;Braverman;Nuclear Engineering and Design,2004

5. Braverman, J.I., Hofmayer, C.H., Morante, R.J., Shteyngart, S., Bezler, P., 2000. Assessment of age-related degradation of structures and passive components for U.S. nuclear power plants. Brookhaven National Laboratory, Upton, NY, NUREG/CR-6679.

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