Prevention of Nonductile Fracture in 6061-T6 Aluminum Nuclear Pressure Vessels

Author:

Yahr G. T.1

Affiliation:

1. Engineering Technology Division, Oak Ridge National Laboratory, Martin Marietta Energy Research, Inc., P.O. Box 2009, Oak Ridge, TN 37831-8051

Abstract

The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Committee has approved rules for the use of 6061-T6 and 6061-T651 aluminum for the construction of Class 1 welded nuclear pressure vessels for temperatures not exceeding 149°C (300°F). Nuclear Code Case N-519 will allow the use of this aluminum in the construction of low-temperature research reactors such as the Advanced Neutron Source. The rules for protection against nonductile fracture are discussed. The basis for a value of 25.3 MPam (23 ksi in.) for the critical or reference stress intensity factor for use in the fracture analysis is presented. Requirements for consideration of the effects of neutron irradiation on the fracture toughness are discussed.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference36 articles.

1. Belfour Stulen, Inc., 1973, Aerospace Structural Metals Handbook, Vol. 3.

2. Albertin, L., and DeMastry, J., 1972, “Post-Irradiation Tensile and Fracture Toughness Properties of 6061-T651 Aluminum Plate,” Astronuclear Program Report, Westinghouse Electric Co., Pittsburgh, PA.

3. Alexander, D. J., 1993, “The Effect of Irradiation on the Mechanical Properties of 6061-T651 Aluminum,” Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175, American Society for Testing and Materials, January 1.

4. ALFRAC, 1993, “Aluminum Fracture Toughness Database, An MPD Network File,” STN International, Columbus, OH.

5. ASME Boiler and Pressure Vessel Code, 1959, Section VIII, “Rules for Construction of Unfired Pressure Vessels.”

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