Research Progress of HT-9 for Fast Reactors

Lyu Liangliang; Li Yuanming; Zhou Yi; Guo Zixuan; Guo Xingkun; Zhang Minjie

doi:10.13832/j.jnpe.2016.S1.0030

Volume 37 Issue S1

Feb. 2025

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Lyu Liangliang, Li Yuanming, Zhou Yi, Guo Zixuan, Guo Xingkun, Zhang Minjie. Research Progress of HT-9 for Fast Reactors[J]. Nuclear Power Engineering, 2016, 37(S1): 30-33. doi: 10.13832/j.jnpe.2016.S1.0030

Citation:

Lyu Liangliang, Li Yuanming, Zhou Yi, Guo Zixuan, Guo Xingkun, Zhang Minjie. Research Progress of HT-9 for Fast Reactors[J]. Nuclear Power Engineering, 2016, 37(S1): 30-33. doi: 10.13832/j.jnpe.2016.S1.0030

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Research Progress of HT-9 for Fast Reactors

doi: 10.13832/j.jnpe.2016.S1.0030

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2016-03-15
Rev Recd Date: 2016-04-25

Available Online: 2025-02-15

Abstract

Abstract

HT-9 is ferritic/martensitic steel with Cr content of 12% and it is an excellent candidate material for fuel clad and duct in liquid metal fast reactors.The research progress of HT-9is introduced.The key application properties needed in liquid metal fast reactor environment are summarized and reviewed.The main problems of using HT-9 in lead cooled fast reactor are analyzed and the developing trend of HT-9 in future is commended.
- Fast reactor,
- Ferritic/martensitic steel,
- HT-9,
- Irradiation performance