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Results 1-5 of 5 (Search time: 0.005 seconds).

NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
1
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

2
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

3
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

4
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

5
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; Na, Kyung-Hwan, JOURNAL OF NUCLEAR MATERIALS, v.556, 2021-12

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