ODS-materials for high temperature applications in advanced nuclear systems-Reference-Cited by-同舟云学术

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ODS-materials for high temperature applications in advanced nuclear systems

Published:2016-12 Issue: Volume:9 Page:22-28
ISSN:2352-1791
Container-title:Nuclear Materials and Energy
language:en
Short-container-title:Nuclear Materials and Energy

Author:

Eiselt C.C.,Schendzielorz H.,Seubert A.,Hary B.,de Carlan Y.,Diano P.,Perrin B.,Cedat D.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics

Reference30 articles.

1. Technology Roadmap Update for Generation IV Nuclear Energy Systems, Gen IV International Forum, January 2014

2. Fast Spectrum Reactors;Waltar,2012

3. Influences of process parameters and microstructure on the fracture mechanisms of ODS steels

4. Characteristic results and prospects of the 13Cr–1W–0.3Ti–0.3Y2O3 ODS steel

5. CEA developments of new ferritic ODS alloys for nuclear applications

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2. Multi-objective optimization assisting three-dimensional quantitative Cahn-Hilliard simulations of microstructure evolution in Fe-Cr alloys during spinodal decomposition;Computational Materials Science;2024-09

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

4. Accident Tolerant Fuel Cladding Materials for Light Water Reactors: Analysis of Neutronic Characteristics;International Journal of Technology;2024-05-17

5. Fabrication and structural, physical, and nuclear radiation shielding properties for Oxide Dispersion-Strengthened (ODS) alloys through Erbium (III) oxide, Samarium (III) oxide, and Praseodymium (III) oxide into 316L matrix;Ceramics International;2024-02

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