A study on the constitutive model of irradiated austenitic stainless steel for the functionality analysis of nuclear internals

Author:

Chung Ilsup

Publisher

Springer Science and Business Media LLC

Subject

Mechanical Engineering,Mechanics of Materials

Reference11 articles.

1. Materials reliability program: Screening, categorization, and ranking of reactor internals components for westinghouse and combustion engineering PWR design (MRP-191), EPRI, Palo Alto, CA, USA (2006).

2. Materials reliability program: Aging management strategies for westinghouse and combustion engineering PWR internal components (MRP-232, Revision 1), EPRI, Palo Alto, CA, USA (2012).

3. Materials reliability program: Functionality analysis for westinghouse and combustion engineering representative PWR internals (MRP-230, Revision 2), EPRI, Palo Alto, CA, USA (2012).

4. Materials reliability program: PWR internals age-related material properties, degradation mechanisms, models, and basis data-state of knowledge (MRP-211), EPRI, Palo Alto, CA, USA (2007).

5. Materials reliability prograwm: Development of material constitutive model for irradiated austenitic stainless steels (MRP-135, Revision 1), EPRI, Palo Alto, CA, USA (2010).

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