|
Home
|
E-Submission/Review
|
Sitemap
|
Editorial Office
|
목적 및 범위
Aims and Scope
저널 정보
About the Journal
편집위원회
Editorial Board
Open Access
편집국
Editorial Office
논문투고안내
Instructions for Authors
연구윤리규정
Research and Publication Ethics
필수 점검 사항
Checklist
논문투고사이트
E-Submission
저작권이양동의서
Copyright Transfer Agreement
발간호 검색
All issues
출판전 논문
Online First
현재 발행 호
Current Issue
많이 읽힌 논문
Most Read Articles
많이 인용된 논문
Most Cited Articles
개별 논문 검색
Korean J. Met. Mater.
Search
저자 색인
Author Index
Korean Journal of Metals and Materials
Search
> Browse Articles > Search
S
u
s
c
e
p
t
i
b
i
l
i
t
y
t
o
S
e
v
e
r
e
P
W
S
C
C
(
p
r
i
m
a
r
y
w
a
t
e
r
s
t
r
e
s
s
c
o
r
r
o
s
i
o
n
c
r
a
c
k
i
n
g
)
o
f
L
T
M
A
(
l
o
w
t
e
m
p
e
r
a
t
u
r
e
m
i
l
l
a
n
n
e
a
l
)
A
l
l
o
y
6
0
0
저온 풀림 처리 Alloy 600이 1차수 응력 부식 균열에 가장 예민한 이유
S
u
n
g
S
o
o
K
i
m
,
J
u
n
g
J
o
n
g
Y
e
o
b
,
Y
o
u
n
g
S
u
k
K
i
m
김성수, 정종엽, 김영석
Korean J. Met. Mater.
2020;58(12):815-821. Published online 2020 Dec 4
DOI:
https://doi.org/10.3365/KJMM.2020.58.12.815
Abstract
It has been proposed that a primary water stress corrosion cracking (PWSCC) in pressurized water reactor (PWR) is governed by a lattice contraction due to a short range ordering reaction in Alloy 600. This leads researcher to think that the kinetics of lattice contraction may control a susceptibility of PWSCC.....
More
Web of Science 4
Crossref 4
1
|
Journal Impact Factor 1.1
> Browse Articles > Search
