Combined Effect of Irradiation and Temperature on the Mechanical Strength of Inconel 800H and AISI 310 Alloys for In-Core Components of a Gen-IV SCWR

Author:

Klassen Robert J.1,Rajakumar Heygaan1

Affiliation:

1. Department of Mechanical and Materials Engineering, University of Western Ontario, 1151 Richmond Street, London, ON N6A 3K7, Canada e-mail:

Abstract

Inconel 800H and AISI 310 alloy samples were exposed to Fe4+ ions to simulate neutron irradiation damage, and then annealed at 400°C and 500°C to study the kinetics of thermal recovery of the irradiation damage. The increase in hardness with ion irradiation and the decrease in hardness due to thermal recovery were recorded. Our findings suggest that under thermal and neutron irradiation conditions envisaged for the Canadian Gen-IV SCWR concept, both alloys will experience significant irradiation hardening; however, this will be concurrently negated by even more rapid thermal recovery of the irradiation damage.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference15 articles.

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2. U.S. DOE Nuclear Energy Research Advisory Committee; the Generation IV International Forum, 2002, “A Technology Roadmap for Generation IV Nuclear Energy Systems,” The Generation IV International Forum (GIF-002-00).

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4. Use of Accelerator Techniques to Study Irradiation Damage;Can. Metall. Q.,1986

5. Modification of Physico-mechanical Properties of Metals and Metallic Coatings by Ion Implantation;Vacuum,1991

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1. Irradiation Issues and Material Selection for Canadian SCWR Components;Journal of Nuclear Engineering and Radiation Science;2018-05-16

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