Oxide dispersion-strengthened/ferrite-martensite steels as core materials for Generation IV nuclear reactors-Reference-Cited by-同舟云学术

Oxide dispersion-strengthened/ferrite-martensite steels as core materials for Generation IV nuclear reactors

Published:2017 Issue: Volume: Page:357-414
ISSN:
Container-title:Structural Materials for Generation IV Nuclear Reactors
language:
Short-container-title:

Author:

Ukai S.,Ohtsuka S.,Kaito T.,de Carlan Y.,Ribis J.,Malaplate J.

Publisher

Elsevier

Reference107 articles.

1. Past research and fabrication conducted at SCK•CEN on ferritic ODS alloys used as cladding for FBR’s fuel pins

2. Structural materials for next generation nuclear systems: Challenges and the path forward

3. POSSIBLE FAST-REACTOR CANNING MATERIAL STRENGTHENED AND STABILIZED BY DISPERSION

4. Développement de nouvelles nuances d'aciers ferritiques/martensitiques pour le gainage d'élément combustible des Réacteurs à Neutrons Rapides au Sodium, Thèse INPG Grenoble;Ratti,2008

5. Review of the studies on fundamental issues in LBE corrosion

Cited by 88 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Manufacturing Oxide Dispersion Strengthened (ODS) steel plate via cold spray and friction stir processing;Journal of Nuclear Materials;2024-08

2. Early corrosion behavior of low carbon 9Cr-ODS steel in high temperature oxygen-saturated lead-bismuth eutectic;Corrosion Science;2024-08

3. Anisotropic creep property related to non-spherical shape of mechanically alloyed powder of oxide dispersion strengthened F82H;Materials Today Communications;2024-08

4. The Irradiation Effects in Ferritic, Ferritic–Martensitic and Austenitic Oxide Dispersion Strengthened Alloys: A Review;Materials;2024-07-10

5. Impact of electron beam welding on the microstructure of PM2000 ODS steel;Fusion Engineering and Design;2024-07