Development of Elevated Temperature Structual Design Standard and Three-Dimensional Seismic Isolation Technology for Advanced Nuclear Power Plant

Inoue, Kazuhiko; Shibamoto, Hiroshi; Takahashi, Kenji; Ikutama, Shinya; Morishita, Masaki; Aoto, Kazumi; Kasahara, Naoto; Asayama, Tai; Kitamura, Seiji

doi:10.3327/jaesj.48.333

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“…As noted elsewhere [92][93][94][95], improved science-based high temperature design rules for irradiated structures are needed to replace current empirical and incomplete design criteria. These improved design rules would be of particular importance to take full advantage of the higher temperature capability of the new RAFM steels.…”

Section: Technical Challenges For Next-generation 8-9%cr Rafmsmentioning

confidence: 99%

Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications

et al. 2017

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Reduced activation ferritic/martensitic steels are currently the most technologically mature option for the structural material of proposed fusion energy reactors. Advanced nextgeneration higher performance steels offer the opportunity for improvements in fusion reactor operational lifetime and reliability, superior neutron radiation damage resistance, higher thermodynamic efficiency, and reduced construction costs. The two main strategies for developing improved steels for fusion energy applications are based on (1) an evolutionary pathway using computational thermodynamics modelling and modified thermomechanical treatments (TMT) to produce higher performance reduced activation ferritic/martensitic (RAFM) steels and (2) a higher risk, potentially higher payoff approach based on powder metallurgy techniques to produce very high strength oxide dispersion strengthened (ODS) steels capable of operation to very high temperatures and with potentially very high resistance to fusion neutron-induced property degradation. The current development status of these nextgeneration high performance steels is summarized, and research and development challenges for the successful development of these materials are outlined. Material properties including temperature-dependent uniaxial yield strengths, tensile elongations, high-temperature thermal creep, Charpy impact ductile to brittle transient temperature (DBTT) and fracture toughness behaviour, and neutron irradiation-induced low-temperature hardening and embrittlement and intermediate-temperature volumetric void swelling (including effects associated with fusionrelevant helium and hydrogen generation) are described for research heats of the new steels.

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Section: Technical Challenges For Next-generation 8-9%cr Rafmsmentioning

confidence: 99%