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DOE OSTI · 3002344

Computational Design of Improved Fast Reactor Cladding

Zhong, Weicheng [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000231589271)·Massey, Caleb [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)]·Yang, Ying [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000164802254)
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Abstract

HT9 ferritic-martensitic (FM) steel has served as a leading candidate for sodium-cooled fast reactor (SFR) cladding due to its favorable resistance to irradiation-induced swelling and good thermal and chemical properties. However, its limited creep strength at temperatures above 600 °C and susceptibility to α′ phase embrittlement under specific conditions could limit its application in next-generation SFRs.

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22 GENERAL STUDIES OF NUCLEAR REACTORS36 MATERIALS SCIENCE97 MATHEMATICS AND COMPUTING

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Zhong, Weicheng [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000231589271), Massey, Caleb [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)], Yang, Ying [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000164802254). 2025-06-01. Computational Design of Improved Fast Reactor Cladding. https://doi.org/10.2172/3002344

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