語系:
繁體中文
English
日文
簡体中文
說明(常見問題)
登入
回首頁
到查詢結果
[ subject:"Nickel alloys" ]
切換:
標籤
|
MARC模式
|
ISBD
Stress corrosion cracking of nickel-...
~
Féron, D.,
Stress corrosion cracking of nickel-based alloys in water-cooled nuclear reactors :the coriou effect /
紀錄類型:
書目-電子資源 : Monograph/item
杜威分類號:
620.1/88
書名/作者:
Stress corrosion cracking of nickel-based alloys in water-cooled nuclear reactors : : the coriou effect // edited by D. Féron, R.W. Staehle.
其他作者:
Féron, D.,
面頁冊數:
1 online resource (xvi, 367 pages) : : illustrations (some color), map.
標題:
Nickel alloys - Stress corrosion.
ISBN:
9780081000625
ISBN:
0081000626
ISBN:
9780081000496
ISBN:
0081000499
書目註:
Includes bibliographical references and index.
摘要、提要註:
Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors: The Coriou Effect presents the latest information on brittle failure of metals in corrosive chemical environments under the influence of tensile stresses. Nickel alloys are more resistant to SCC as well as high temperatures and have been widely used in more challenging environments such as nuclear power plants. However, these alloys can suffer SCC under certain conditions, resulting in component failure. A key figure in understanding the mechanisms of SCC in nickel alloys in water-cooled nuclear reactors is Henri Coriou of the CEA, France's leading center for nuclear research. This book assesses his work in the context of the latest research on SCC in nickel alloys in nuclear power plants. Up-to-date reviews of recent research findings from leading experts in the field Authoritative and comprehensively reviewed by the Working Party 4 on Nuclear CorrosionShowcases the excellent quality and technical accomplishments of Henri Coriou and CEA.
電子資源:
https://
www.sciencedirect.com/science/book/9780081000496
Stress corrosion cracking of nickel-based alloys in water-cooled nuclear reactors :the coriou effect /
Stress corrosion cracking of nickel-based alloys in water-cooled nuclear reactors :
the coriou effect /edited by D. Féron, R.W. Staehle. - 1 online resource (xvi, 367 pages) :illustrations (some color), map. - Woodhead Publishing series in EFC ;number 67. - Woodhead Publishing series in EFC ;no. 67..
Includes bibliographical references and index.
Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors: The Coriou Effect presents the latest information on brittle failure of metals in corrosive chemical environments under the influence of tensile stresses. Nickel alloys are more resistant to SCC as well as high temperatures and have been widely used in more challenging environments such as nuclear power plants. However, these alloys can suffer SCC under certain conditions, resulting in component failure. A key figure in understanding the mechanisms of SCC in nickel alloys in water-cooled nuclear reactors is Henri Coriou of the CEA, France's leading center for nuclear research. This book assesses his work in the context of the latest research on SCC in nickel alloys in nuclear power plants. Up-to-date reviews of recent research findings from leading experts in the field Authoritative and comprehensively reviewed by the Working Party 4 on Nuclear CorrosionShowcases the excellent quality and technical accomplishments of Henri Coriou and CEA.
ISBN: 9780081000625Subjects--Topical Terms:
716251
Nickel alloys
--Stress corrosion.Index Terms--Genre/Form:
336502
Electronic books.
LC Class. No.: TA480.N6
Dewey Class. No.: 620.1/88
Stress corrosion cracking of nickel-based alloys in water-cooled nuclear reactors :the coriou effect /
LDR
:02295nmm a2200313 i 4500
001
493636
006
m o d
007
cr cnu|unuuu||
008
210205t20162016enkab ob 001 0 eng d
020
$a
9780081000625
$q
(electronic bk.)
020
$a
0081000626
$q
(electronic bk.)
020
$a
9780081000496
020
$a
0081000499
035
$a
(OCoLC)936379392
$z
(OCoLC)939262207
035
$a
els19100136
040
$a
N$T
$b
eng
$e
rda
$e
pn
$c
N$T
$d
IDEBK
$d
YDXCP
$d
N$T
$d
CDX
$d
OPELS
$d
OCLCF
$d
EBLCP
$d
KNOVL
$d
VLB
$d
ZCU
$d
UPM
$d
OCLCA
$d
OCLCQ
$d
U3W
$d
CEF
$d
RRP
$d
OCLCQ
041
0
$a
eng
050
4
$a
TA480.N6
082
0 4
$a
620.1/88
$2
23
245
0 0
$a
Stress corrosion cracking of nickel-based alloys in water-cooled nuclear reactors :
$b
the coriou effect /
$c
edited by D. Féron, R.W. Staehle.
264
1
$a
Duxford, UK :
$b
Elsevier, Woodhead Publishing,
$c
[2016]
264
4
$c
©2016
300
$a
1 online resource (xvi, 367 pages) :
$b
illustrations (some color), map.
336
$a
text
$b
txt
$2
rdacontent
337
$a
computer
$b
c
$2
rdamedia
338
$a
online resource
$b
cr
$2
rdacarrier
490
1
$a
Woodhead Publishing series in EFC ;
$v
number 67
504
$a
Includes bibliographical references and index.
520
$a
Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors: The Coriou Effect presents the latest information on brittle failure of metals in corrosive chemical environments under the influence of tensile stresses. Nickel alloys are more resistant to SCC as well as high temperatures and have been widely used in more challenging environments such as nuclear power plants. However, these alloys can suffer SCC under certain conditions, resulting in component failure. A key figure in understanding the mechanisms of SCC in nickel alloys in water-cooled nuclear reactors is Henri Coriou of the CEA, France's leading center for nuclear research. This book assesses his work in the context of the latest research on SCC in nickel alloys in nuclear power plants. Up-to-date reviews of recent research findings from leading experts in the field Authoritative and comprehensively reviewed by the Working Party 4 on Nuclear CorrosionShowcases the excellent quality and technical accomplishments of Henri Coriou and CEA.
650
0
$a
Nickel alloys
$x
Stress corrosion.
$3
716251
655
4
$a
Electronic books.
$2
local
$3
336502
700
1
$a
Féron, D.,
$e
editor.
$3
716248
700
1
$a
Staehle, R. W.,
$d
1934-2017,
$e
editor.
$3
716249
830
0
$a
Woodhead Publishing series in EFC ;
$v
no. 67.
$3
716250
856
4 0
$u
https://www.sciencedirect.com/science/book/9780081000496
筆 0 讀者評論
多媒體
多媒體檔案
https://www.sciencedirect.com/science/book/9780081000496
評論
新增評論
分享你的心得
Export
取書館別
處理中
...
變更密碼
登入