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Investigating creep behavior of Ni–Cr–W alloy pressurized tube at 950 °C by using in-situ creep testing system

  • Published:2020-07 Issue:7 Volume:52 Page:1481-1485
  • ISSN:1738-5733
  • Container-title:Nuclear Engineering and Technology
  • language:en
  • Short-container-title:Nuclear Engineering and Technology

Author:

Zhong Yang,Lan Kuan-Che,Lee Hoon,Zhou Bomou,Wang Yong,Tsang D.K.L.,Stubbins James F.

Funder

Chinese Academy of Sciences

China Scholarship Council

University of Illinois at Urbana-Champaign

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference26 articles.

1. The Very High Temperature Reactor: A Technical Summary;Chapin,2004

2. Updated Generation IV Reactors Integrated Materials Technology Program Plan;Corwin,2004

3. A review on current status of alloys 617 and 230 for Gen IV nuclear reactor internals and heat exchangers;Ren;J. Press. Vessel Technol.,2009

4. Mechanism of creep deformation of Alloy 230 based on microstructural analyses;Chatterjee;Mater. Sci. Eng. A,2010

5. A comparison of the microstructure and creep behavior of cold rolled HAYNES® 230 alloy™ and HAYNES® 282 alloy™;Boehlert;Mater. Sci. Eng. A,2011

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