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1
Characterization of oxide layers formed on type 316 stainless steel exposed to the simulated PWR primary water environment with varying dissolved hydrogen and zinc concentrations

Lee, Hyeon Bae; Chen, Junjie; Meng, Shu; Jang, Changheui; Park, Su Hyun; Xiao, Qian; Lee, Ho Jung; et al, JOURNAL OF NUCLEAR MATERIALS, v.556, 2021-12

2
Corrosion behavior of Fe-based candidate accident tolerant fuel cladding alloys in spent fuel pool environment - Effect of prior corrosion

Xiao, Qian; Jang, Changheui; Kim, Chaewon; Chen, Junjie; Jeong, Chaewon; Hwan, Sung, JOURNAL OF NUCLEAR MATERIALS, v.548, 2021-05

3
Corrosion behavior of stainless steels in simulated PWR primary water: The effect of composition and matrix phases

Xiao, Qian; Jang, Changheui; Kim, Chaewon; Kim, Hyunmyung; Chen, Junjie; Lee, Hyeon Bae, CORROSION SCIENCE, v.177, pp.108991, 2020-12

4
Effect of heat treatment on corrosion behaviour of additively manufactured 316L stainless steel in high-temperature water

Xiao, Qian; Chen, Junjie; Lee, Hyeon Bae; Jang, Changheui; Jang, Kyungnam, CORROSION SCIENCE, v.210, 2023-01

5
Effect of thermal ageing on the corrosion behaviour of austenitic stainless steel welds in the simulated PWR primary water

Chen, Junjie; Jang, Changheui; Kong, Byeon Seo; Xiao, Qian; Subramanian, Gokul Obulan; Kim, Ho Sub; Shin, Ji Ho, CORROSION SCIENCE, v.172, pp.108730, 2020-08

6
Enhanced pitting resistance of directed energy deposition 316L stainless steel by post-manufacturing heat treatment

Chen, Junjie; Xiao, Qian; Lee, Hyeon Bae; Jeong, Chaewon; Jang, Kyungnam; Jang, Changheui, NPJ MATERIALS DEGRADATION, v.6, no.1, 2022-04

7
Evaluation of thermal aging activation energies based on multi-scale mechanical property tests for an austenitic stainless steel weld beads

Jeong, Chaewon; Kong, Byeong Seo; Shin, Ji Ho; Chen, Junjie; Xiao, Qian; Jang, Changheui, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.835, 2022-02

8
On the feasibility of duplex stainless steel 2205 as an accident tolerant fuel cladding material for light water reactors

Xiao, Qian; Kim, Chaewon; Jang, Changheui; Jeong, Chaewon; Kim, Hyunmyung; Chen, Junjie; Heo, Woong, JOURNAL OF NUCLEAR MATERIALS, v.557, 2021-12

9
The corrosion behaviour of alloy 690 tube in simulated PWR secondary water with the effect of solid diffusing hydrogen

Chen, Junjie; Lu, Zhanpeng; Meng, Fanjiang; Xu, Xuelian; Xiao, Qian; Kim, Ho-Sub; Jang, Changheui, JOURNAL OF NUCLEAR MATERIALS, v.517, pp.179 - 191, 2019-04

10
The effect of zinc addition on corrosion behavior of stainless steels with different phases in simulated PWR primary water

Park, Su Hyun; Lee, Hyeon Bae; Kim, Chaewon; Okonkwo, Bright O.; Jang, Changheui; Xiao, Qian, CORROSION SCIENCE, v.209, 2022-12

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