FeCrAl and Zr alloys joined using hot isostatic pressing for fusion energy applications-Reference-Cited by-同舟云学术

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FeCrAl and Zr alloys joined using hot isostatic pressing for fusion energy applications

Published:2016-11 Issue: Volume:109-111 Page:561-564
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Park Dong Jun,Kim Hyun Gil,Park Jeong Yong,Jung Yang Il,Park Jung Hwan,Koo Yang Hyun

Funder

Korea government (MSIP)

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference25 articles.

1. Status of reduced activation ferritic/martensitic steel development;Baluc;J. Nucl. Mater.,2007

2. Hydrogen isotopes transport parameters in fusion reactor materials;Serra;J. Nucl. Mater.,1998

3. Tensile behavior of EUROFER ODS steel after neutron irradiation up to16.3dpa between 250 and 450°C;Materna-Morris;Fusion Eng. Des.,2015

4. Blanket material and technology developments toward DEMO under the broader approach framework;Nishitani;Fusion Eng. Des.,2014

5. A review on the potential use of austenitic stainless steels in nuclear fusion reactors;Şahin;J. Fusion Energy,2008

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1. Microstructural evolution of the Cr/FeCrAl coated Zircaloy-4 under simulated PWR and high-temperature steam oxidation environments;Journal of Nuclear Materials;2024-11

2. High-Temperature Oxidation, Corrosion, and Wear Resistance of Cr‐xAl Laser Coated on Metal Zr Surface;Journal of Materials Engineering and Performance;2024-09-06

3. Recent Advances in Joining of Zirconium and Zirconium Alloy for Nuclear Industry;Metals and Materials International;2024-05-03

4. Improved oxidation resistance of Cr/FeCrAl coating on Zr alloy in high-temperature steam environment;Surface and Coatings Technology;2023-11

5. Effects of long-time annealing on the microstructures and shear tensile strengths of diffusion-bonded FeCrAl/N18 clad plates;Nuclear Materials and Energy;2022-09

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