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DOE OSTI · 2481588

Preliminary HEA Solid Phase Processing Development Report

van Rooyen, Isabella Johanna·Soulami, Ayoub·Li, Lei·Nartu, Mohan Sai Kiran Kumar Yadav·Meher, Subhashish·Wierschke, Jonathan B.·Fernandez dos Santos, Jorge·Komarasamy, Mageshwari
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Abstract

The development of high temperature fuel cladding materials to withstand a variety of extreme environments have received much attention. Several potential materials systems that have been identified for the fuel systems and core structural materials application in advanced reactor systems are ferritic/martensitic steel (e.g., HT9), austenitic stainless steels (e.g., 316 LN), oxide-dispersion strengthened steels (e.g., 12 YWT), Ni-based alloys and ceramic-based composites depending on the type of the reactors. Though these material systems have promising properties conducive for radiation-resistant performance, they suffer beyond the design-limit from one or more damage processes such as void swelling, radiation embrittlement, phase instability, corrosion, and limited creep life.

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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS36 MATERIALS SCIENCE

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van Rooyen, Isabella Johanna, Soulami, Ayoub, Li, Lei, Nartu, Mohan Sai Kiran Kumar Yadav, Meher, Subhashish, Wierschke, Jonathan B., Fernandez dos Santos, Jorge, Komarasamy, Mageshwari. 2023-09-01. Preliminary HEA Solid Phase Processing Development Report. https://doi.org/10.2172/2481588

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