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A Study on Corrosion Behaviors for Life-Prediction of Structural Materials in Lead Fast Reactors
납냉각 고속로 구조 재료의 수명 예측을 위한 부식 거동 연구

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Authors
이승기
Advisor
황일순
Major
공과대학 원자핵공학과
Issue Date
2013-02
Publisher
서울대학교 대학원
Keywords
LBEcorrosionduplex oxide layerspallation of oxide layersCr-depletionself-healing
Description
학위논문 (박사)-- 서울대학교 대학원 : 원자핵공학과, 2013. 2. 황일순.
Abstract
A corrosion study has been made in this thesis in order to predict corrosion behaviors based on mechanistic understanding for typical materials of construction, including ferritic / martensitic stainless steel, T91 and HT9, as well as austenitic stainless steels, SS316L. Corrosion tests were performed at temperatures up to 600℃ in order to understand the corrosion behavior in lead-bismuth eutectic liquid. Based on test results, the process of corrosion at temperatures up to 600℃ is understood, as follows:
1. The formation of duplex oxide layers (outer magnetite layer and inner Fe-Cr spinel) and their growth with time
2. Removal of outer magnetite accompanied with lead penetration
3. The fracture of inner Fe-Cr spinel (corrosion barrier) due to mechanical stresses with oxide growth
4. Re-passivation of Fe-Cr spinel by oxidation
5. The failure of Fe-Cr spinel layer by Cr-depletion along grain boundaries
6. The start of dissolution: LBE penetration into metal substrate through grain boundaries
In order to avoid active corrosion, two criteria based on relationship between Cr-depletion and passivity of Cr-oxide are proposed as followings
 Allowable operation temperature limit for studied materials predicted by thermochemical calculation of re-passivity considered chemical composition of structural materials
 Operation time to loss of structural integrity by oxide failure is obtained from corrosion test result.
Conventional steels forming Cr-oxide as protect layer can give good performance in lead or lead alloy at temperatures up to about 470℃ before oxide layer grows by about 44μm for ferritic / martensitic steels (T91 and HT9) and about 25μm for austenitic stainless steels (SS316L). Al-containing steels or Si-containing steels forming Al-oxide or Si-oxide as corrosion barrier should be applied to lead or lead alloy at temperatures above 470℃ due to their excellent corrosion resistance.
Considered operation conditions of under developing LFR, such as MYRRHA, corrosion problem can be overcome by proven ferritic / martensitic steel and austenitic stainless steels. Furthermore, Al-containing steels or Si-containing steels can be commercialized by methods of coating or functionally graded composite in the near future.
Language
English
URI
https://hdl.handle.net/10371/118222
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College of Engineering/Engineering Practice School (공과대학/대학원)Dept. of Energy Systems Engineering (에너지시스템공학부)Nuclear Engineering (원자핵공학전공)Theses (Ph.D. / Sc.D._원자핵공학과)
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