Evaluation of threshold stress of the MA957 ODS ferrtic alloy-Reference-Cited by-同舟云学术

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Evaluation of threshold stress of the MA957 ODS ferrtic alloy

Published:2009-04 Issue: Volume:386-388 Page:511-514
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Sakasegawa H.,Chaffron L.,Legendre F.,Brocq M.,Boulanger L.,Poissonnet S.,de Carlan Y.,Bechade J.,Cozzika T.,Malaplate J.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference27 articles.

1. Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys

2. Present development status of EUROFER and ODS-EUROFER for application in blanket concepts

3. Irradiation creep and swelling from 400 to 600 °C of the oxide dispersion strengthened ferritic alloy MA957

4. Assessment of ODS-14%Cr ferritic alloy for high temperature applications

5. Production and Properties of Nano-scale Oxide Dispersion Strengthened (ODS) 9Cr Martensitic Steel Claddings

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1. The Constant-Stress, Constant-Heating-Rate Behavior of an Additively Manufactured ODS Superalloy;Metallurgical and Materials Transactions A;2024-04-02

2. Transformation of oxide nanoparticles in a nickel-based ODS alloy aged at 1000 °C;Journal of Materials Science;2023-10

3. Mechanisms of plastic deformation and fracture in coarse grained Fe–10Al–4Cr–4Y2O3 ODS nanocomposite at 20–1300°C;Journal of Materials Research and Technology;2023-05

4. Nanosized oxide phases in oxide-dispersion-strengthened steel PM2000;Philosophical Magazine;2021-10-01

5. Early-stage thermal ageing behavior of 12Cr, 12Cr–7Al and 18Cr–9Al ODS steels;Journal of Nuclear Materials;2020-07

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