Intermediate heat exchanger (IHX), which transfers the heat generated in the reactor core to the secondary loop, is one of the key structural components of the very high-temperature gas-cooled reactor (VHTR). The Ni-based superalloy GH3128 has good high-temperature strength and so is a promising main structural material for the IHX. In this paper, the flow stress behaviors and the deformation microstructure of superalloy GH3128 were investigated by high-temperature compression tests conducted at various temperatures (950–1150 °C) and strain rates (0.001–10 s−1), and the processing maps were analyzed in order to establish the hot deformation constitutive model and obtain the optimum hot forming condition. The results show that (1) both flow stresses and peak flow stresses increase along with the increase of strain rate or decrease of temperature, (2) GH3128 has excellent hot workability, (3) the dynamic recovery (DRV) plays the dominant role during the dynamic softening process due to the high stack fault energy, and (4) the optimum hot forming condition of GH3128 should be defined in the temperature of 1150 °C and strain rate range of 0.01–0.056 s−1. This work contributes to the application of GH3128 alloy on IHX structure.
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April 2017
Research-Article
Research on the High-Temperature Hot Compressive Deformation Behavior of Ni-Based Superalloy GH3128
Xi Zhao,
Xi Zhao
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Room A201, Energy Science Building,
Beijing 100084, China
e-mail: zhaoxithu@163.com
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Room A201, Energy Science Building,
Beijing 100084, China
e-mail: zhaoxithu@163.com
Search for other works by this author on:
Kun Yuan,
Kun Yuan
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Room C103, Energy Science Building,
Beijing 100084, China
e-mail: kyuan@tsinghua.edu.cn
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Room C103, Energy Science Building,
Beijing 100084, China
e-mail: kyuan@tsinghua.edu.cn
Search for other works by this author on:
Yu Zhou,
Yu Zhou
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Room 1210, Huaye Building,
Beijing 100084, China
e-mail: yuzhou@tsinghua.edu.cn
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Room 1210, Huaye Building,
Beijing 100084, China
e-mail: yuzhou@tsinghua.edu.cn
Search for other works by this author on:
Fu Li
Fu Li
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Energy Science Building,
Beijing 100084, China
e-mail: lifu@tsinghua.edu.cn
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Energy Science Building,
Beijing 100084, China
e-mail: lifu@tsinghua.edu.cn
Search for other works by this author on:
Xi Zhao
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Room A201, Energy Science Building,
Beijing 100084, China
e-mail: zhaoxithu@163.com
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Room A201, Energy Science Building,
Beijing 100084, China
e-mail: zhaoxithu@163.com
Kun Yuan
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Room C103, Energy Science Building,
Beijing 100084, China
e-mail: kyuan@tsinghua.edu.cn
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Room C103, Energy Science Building,
Beijing 100084, China
e-mail: kyuan@tsinghua.edu.cn
Yu Zhou
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Room 1210, Huaye Building,
Beijing 100084, China
e-mail: yuzhou@tsinghua.edu.cn
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Room 1210, Huaye Building,
Beijing 100084, China
e-mail: yuzhou@tsinghua.edu.cn
Fu Li
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Energy Science Building,
Beijing 100084, China
e-mail: lifu@tsinghua.edu.cn
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Tsinghua University,
Energy Science Building,
Beijing 100084, China
e-mail: lifu@tsinghua.edu.cn
1Corresponding author.
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received February 23, 2016; final manuscript received July 3, 2016; published online September 27, 2016. Assoc. Editor: Haofeng Chen.
J. Pressure Vessel Technol. Apr 2017, 139(2): 021401 (8 pages)
Published Online: September 27, 2016
Article history
Received:
February 23, 2016
Revised:
July 3, 2016
Citation
Zhao, X., Yuan, K., Zhou, Y., and Li, F. (September 27, 2016). "Research on the High-Temperature Hot Compressive Deformation Behavior of Ni-Based Superalloy GH3128." ASME. J. Pressure Vessel Technol. April 2017; 139(2): 021401. https://doi.org/10.1115/1.4034147
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