Mechanical property changes in reactor vessel materials thermally aged for 209 000 H at 260°C

Journal of ASTM International

Volumn 3, Issue 2, 2006, Pages

  Gunawardane, Heshan P ^a   Hall, J Brian ^a   Rosinski, Stan T ^b  

^a AREVA NP INC   (United States)

^b Welding and Repair Technology Center   (United States)

Author keywords

Charpy; Fracture toughness; Reactor vessel materials; Tensile; Thermal aging; Transition temperature

Indexed keywords

FORGING; FRACTURE TOUGHNESS; MATERIALS TESTING; PRESSURE VESSELS; TENSILE TESTING;

CHARPY; REACTOR VESSEL MATERIALS; TENSILE; THERMAL AGING; TRANSITION TEMPERATURES;

CONTAINMENT VESSELS;

EID: 34250338962     PISSN: None     EISSN: 1546962X     Source Type: Journal    
DOI: 10.1520/JAI12430     Document Type: Article

References (5)

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3. DeVan, M. J., Lowe, Jr., A. L., and Wade, C. S., "Evaluation of Thermal-Aged Plates, Forgings, and Submerged-Arc Weld Metals," Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175, A. S. Kumar, D. S. Gelles, R. K. Nanstad, and E. A. Little, Eds., American Society for Testing and Materials, Philadelphia, 1993, pp. 268-282.
4. Materials Reliability Program: Validation and Use of ASTM E 900-02 for Reactor Pressure Vessel Integrity (MRP-86), EPRI, Palo Alto, CA, 2003.
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