Publication:

The microstructure and associated tensile properties of irradiated fcc and bcc metals

cris.lastimport.scopus

2025-06-03T16:54:26Z

cris.legacyId

119713

cris.virtual.department

PH-SB

cris.virtual.department

EDMX-ENS

cris.virtual.parent-organization

UHD

cris.virtual.parent-organization

SB

cris.virtual.parent-organization

EPFL

cris.virtual.sciperId

104444

cris.virtual.sciperId

106649

cris.virtual.sciperId

109859

cris.virtual.unitId

3189

cris.virtual.unitId

10194

cris.virtual.unitManager

Dyson, Paul Joseph

cris.virtual.unitManager

Ricci, Paolo

cris.virtual.unitManager

Coda, Stefano

cris.virtual.unitManager

Stiebrina, Dace

cris.virtual.unitManager

Amstad, Esther

cris.virtualsource.author-scopus

92c37bf7-a6a8-4c4e-8aa7-9408047a2e6b

cris.virtualsource.author-scopus

b7c2d8bb-973b-443c-9a42-9d41a25cd7b0

cris.virtualsource.author-scopus

0a7a320a-434a-4f37-a944-b355665d52e9

cris.virtualsource.department

92c37bf7-a6a8-4c4e-8aa7-9408047a2e6b

cris.virtualsource.department

b7c2d8bb-973b-443c-9a42-9d41a25cd7b0

cris.virtualsource.department

0a7a320a-434a-4f37-a944-b355665d52e9

cris.virtualsource.orcid

92c37bf7-a6a8-4c4e-8aa7-9408047a2e6b

cris.virtualsource.orcid

b7c2d8bb-973b-443c-9a42-9d41a25cd7b0

cris.virtualsource.orcid

0a7a320a-434a-4f37-a944-b355665d52e9

cris.virtualsource.parent-organization

0b6d7c2b-7f7c-42e5-95be-88ece2cd2eff

cris.virtualsource.parent-organization

9aaafeb2-7497-4a6b-a128-d469748b898b

cris.virtualsource.parent-organization

9aaafeb2-7497-4a6b-a128-d469748b898b

cris.virtualsource.parent-organization

9aaafeb2-7497-4a6b-a128-d469748b898b

cris.virtualsource.rid

92c37bf7-a6a8-4c4e-8aa7-9408047a2e6b

cris.virtualsource.rid

b7c2d8bb-973b-443c-9a42-9d41a25cd7b0

cris.virtualsource.rid

0a7a320a-434a-4f37-a944-b355665d52e9

cris.virtualsource.sciperId

92c37bf7-a6a8-4c4e-8aa7-9408047a2e6b

cris.virtualsource.sciperId

b7c2d8bb-973b-443c-9a42-9d41a25cd7b0

cris.virtualsource.sciperId

0a7a320a-434a-4f37-a944-b355665d52e9

cris.virtualsource.unitId

0b6d7c2b-7f7c-42e5-95be-88ece2cd2eff

cris.virtualsource.unitId

9aaafeb2-7497-4a6b-a128-d469748b898b

cris.virtualsource.unitManager

81ca2c4d-7c1c-43ad-b2f7-90075bb54133

cris.virtualsource.unitManager

0b6d7c2b-7f7c-42e5-95be-88ece2cd2eff

cris.virtualsource.unitManager

9aaafeb2-7497-4a6b-a128-d469748b898b

cris.virtualsource.unitManager

9aaafeb2-7497-4a6b-a128-d469748b898b

cris.virtualsource.unitManager

9aaafeb2-7497-4a6b-a128-d469748b898b

cris.virtualsource.unitManager

b1606717-df3c-42dc-99fa-5b7f97ca6c8d

datacite.rights

metadata-only

dc.contributor.author

Victoria, M.

dc.contributor.author

Baluc, N.

dc.contributor.author

Bailat, C.

dc.contributor.author

Dai, Y.

dc.contributor.author

Luppo, M. I.

dc.contributor.author

Schaeublin, R.

dc.contributor.author

Singh, B. N.

dc.date.accessioned

2008-04-16T13:10:11

dc.date.available

2008-04-16T13:10:11

dc.date.created

2008-04-16

dc.date.issued

2000

dc.date.modified

2025-05-29T23:51:28.952226Z

dc.description.abstract

The differences and similarities of behaviour between fee and bcc metals after irradiation have been investigated. For this purpose, fee Cu, Pd and 304 stainless steel and bcc Fe, Mo and Mo-5% Re were irradiated with either neutrons or 590 MeV protons at temperatures below recovery stage V. It is shown that a dense population of defect clusters (up to 10(22)-10(24) m(-3)) develops, the type of cluster formed depending apparently on the stacking fault energy. In the case of stacking fault tetrahedra formed in Cu, their size is independent of dose, while interstitial loops in stainless steel grow at neutron doses higher than 1 dpa. The defect microstructure is found to be independent of the recoil energy spectra in this temperature region, but shows a very strong dependence on the type of crystalline structure. The results of tensile testing indicate the presence of radiation hardening, starting at very low doses as an upper yield point develops followed by a (serrated) yield region. The main deformation mode observed is dislocation channeling. The hardening is modelled in terms of the initial dislocation locking by the irradiation-induced defects followed by the dispersed hardening induced by the global distribution of clusters in the matrix. (C) 2000 Published by Elsevier Science B.V. All rights reserved.

dc.description.sponsorship

CRPP

dc.description.sponsorship

SPC

dc.identifier.doi

10.1016/S0022-3115(99)00203-2

dc.identifier.isi

WOS:000084543400013

dc.identifier.uri

https://infoscience.epfl.ch/handle/20.500.14299/21612

dc.relation.issn

0022-3115

dc.relation.journal

Journal of Nuclear Materials

dc.title

The microstructure and associated tensile properties of irradiated fcc and bcc metals

dc.type

text::journal::journal article::research article

dspace.entity.type

Publication

dspace.legacy.oai-identifier

oai:infoscience.tind.io:119713

epfl.legacy.itemtype

Journal Articles

epfl.legacy.submissionform

ARTICLE

epfl.oai.currentset

SB

epfl.oai.currentset

OpenAIREv4

epfl.oai.currentset

article

epfl.peerreviewed

REVIEWED

epfl.publication.version

http://purl.org/coar/version/c_970fb48d4fbd8a85

epfl.writtenAt

EPFL

oaire.citation.endPage

122

oaire.citation.startPage

114

oaire.citation.volume

276

Files

License bundle

Now showing 1 - 1 of 1
Loading...
Thumbnail Image
Name:
license.txt
Size:
1.71 KB
Format:
Item-specific license agreed to upon submission
Description:

Collections