Zobrazeno 1 - 10
of 61
pro vyhledávání: '"X Averty"'
Publikováno v:
Journal of Nuclear Materials. 417:99-103
Four 9Cr Reduced Activation martensitic steels, two ODS-FeCr alloys and one conventional 9Cr martensitic steel were irradiated in BOR-60 reactor to doses ranging from 40 to 78 dpa at 325 °C. Tensile, impact tests and fracture surface examinations we
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f2583a998bd5c5e1619e480a4e44664b
https://doi.org/10.1016/j.jnucmat.2010.12.203
https://doi.org/10.1016/j.jnucmat.2010.12.203
Publikováno v:
Journal of Nuclear Materials. 415:306-310
In the European EUROTRANS/DEMETRA program, the synergistic effect of radiation damage and helium on microstructure and mechanical properties of two 9Cr 1Mo ferritic/martensitic (FM) steels T91 and EM10 was evaluated after irradiation in SINQ targets.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2cd3a0c26ab9ef5df17298dd0beb8687
https://doi.org/10.1016/j.jnucmat.2011.04.029
https://doi.org/10.1016/j.jnucmat.2011.04.029
Publikováno v:
Journal of Nuclear Materials. :345-348
The tensile properties of mechanically-alloyed oxide dispersion strengthened MA957 steel were measured at room temperature following irradiation in the SINQ spallation target up to almost 20 dpa corresponding to an accumulated helium content of about
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8befbc18a4827c2675a38e060cc87036
https://doi.org/10.1016/j.jnucmat.2008.12.132
https://doi.org/10.1016/j.jnucmat.2008.12.132
Publikováno v:
Journal of Nuclear Materials. :236-240
In blankets of a fusion power plant 14 MeV neutrons produce displacement damage, dpa, and helium and hydrogen. Martensitic steels offer the advantages of low swelling and reduced helium embrittlement compared to austenitic steels. Reduced activation
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::04a9fa44020ae5a649cdd43b752cca63
https://doi.org/10.1016/j.jnucmat.2008.12.329
https://doi.org/10.1016/j.jnucmat.2008.12.329
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2008, 378, pp.60-69. ⟨10.1016/j.jnucmat.2008.04.017⟩
Journal of Nuclear Materials, Elsevier, 2008, 378, pp.60-69. ⟨10.1016/j.jnucmat.2008.04.017⟩
This paper presents a unified phenomenological model to describe the anisotropic viscoplastic mechanical behavior of cold-worked stress relieved (CWSR) Zircaloy-4 fuel claddings submitted to reactivity initiated accident (RIA) loading conditions. The
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c6d40babb25b3f8d30ad127fddb4ea0d
https://doi.org/10.1016/j.jnucmat.2008.04.017
https://doi.org/10.1016/j.jnucmat.2008.04.017
Publikováno v:
Engineering Fracture Mechanics. 75:3570-3580
Ferritic-martensitic steels are prime candidate materials for future reactors. We present here the results of a study on the effects of helium implantation on the fracture behavior of 9Cr (T91) martensitic steels. Three-points static bending tests we
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fe5eb168133bf5594de898d43c9bc673
https://doi.org/10.1016/j.engfracmech.2007.02.019
https://doi.org/10.1016/j.engfracmech.2007.02.019
Publikováno v:
Journal of Nuclear Materials. :411-416
An experimental characterization was conducted of helium effects on the mechanical properties of a 9Cr martensitic steel. Six sub-size Charpy samples were implanted in the notch region at 250 °C with 0.25 at.% helium and subsequently tested in 3-poi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6dd3a1ed689ddde42845fb7ef4f21691
https://doi.org/10.1016/j.jnucmat.2007.03.122
https://doi.org/10.1016/j.jnucmat.2007.03.122
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, 2015, 465, pp.20-27. ⟨10.1016/j.jnucmat.2015.05.023⟩
Journal of Nuclear Materials, Elsevier, 2015, 465, pp.20-27. ⟨10.1016/j.jnucmat.2015.05.023⟩
Journal of Nuclear Materials, 2015, 465, pp.20-27. ⟨10.1016/j.jnucmat.2015.05.023⟩
Journal of Nuclear Materials, Elsevier, 2015, 465, pp.20-27. ⟨10.1016/j.jnucmat.2015.05.023⟩
The hardening and the embrittlement under neutron irradiation of an A508 type RPV steel considering three different microstructures (bainite, bainite-martensite and martensite)have been investigated These microstructures were obtained by quenching af
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c503f26eb375da297c5a7166eda77402
https://cea.hal.science/cea-02385950/document
https://cea.hal.science/cea-02385950/document
Publikováno v:
Journal of Nuclear Materials. 356:78-87
In order to investigate helium effects on the fracture properties of martensitic mod 9Cr–1Mo (T91) steel, miniature Charpy specimens were implanted at 250 °C in the notch region to 0.25 at.% helium using a degraded 34 MeV 3He ion beam and subseque
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bcca544cdf9cf97271c5358e60d23d8a
https://doi.org/10.1016/j.jnucmat.2006.05.004
https://doi.org/10.1016/j.jnucmat.2006.05.004
Publikováno v:
Journal of Nuclear Materials. :333-337
The present paper evaluates the mechanical behaviour of the ODS-ferritic alloy, Fe–14Cr–1Ti–0.25Y2O3 (MA957), produced with two microstructures characterized by different grain sizes and degree of crystallographic texture. Tensile, creep and im
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ef9e9cd1b2b2ed570c5c5a19ff279d81
https://doi.org/10.1016/j.jnucmat.2004.05.004
https://doi.org/10.1016/j.jnucmat.2004.05.004