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Title: Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel

Authors:
ORCiD logo; ; ;
Publication Date:
Sponsoring Org.:
USDOE
OSTI Identifier:
1353271
Grant/Contract Number:
NE0000639
Resource Type:
Journal Article: Published Article
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 491; Journal Issue: C; Related Information: CHORUS Timestamp: 2017-06-10 07:52:04; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
Netherlands
Language:
English

Citation Formats

Zheng, Ce, Auger, Maria A., Moody, Michael P., and Kaoumi, Djamel. Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel. Netherlands: N. p., 2017. Web. doi:10.1016/j.jnucmat.2017.04.040.
Zheng, Ce, Auger, Maria A., Moody, Michael P., & Kaoumi, Djamel. Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel. Netherlands. doi:10.1016/j.jnucmat.2017.04.040.
Zheng, Ce, Auger, Maria A., Moody, Michael P., and Kaoumi, Djamel. 2017. "Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel". Netherlands. doi:10.1016/j.jnucmat.2017.04.040.
@article{osti_1353271,
title = {Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel},
author = {Zheng, Ce and Auger, Maria A. and Moody, Michael P. and Kaoumi, Djamel},
abstractNote = {},
doi = {10.1016/j.jnucmat.2017.04.040},
journal = {Journal of Nuclear Materials},
number = C,
volume = 491,
place = {Netherlands},
year = 2017,
month = 8
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record at 10.1016/j.jnucmat.2017.04.040

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  • Ferritic/Martensitic (F/M) steels with high Cr content posses the high temperature strength and low swelling rates required for advanced nuclear reactor designs. Radiation induced segregation (RIS) occurs in F/M steels due to solute atoms preferentially coupling to point defect fluxes to defect sinks, such as grain boundaries (GBs). The RIS response of F/M steels and austenitic steels has been shown to be dependent on the local structure of GBs but has only been demonstrated in ion irradiated specimens. A 9 wt. % Cr model alloy steel was irradiated to 3 dpa using neutrons at the Advanced Test Reactor (ATR) tomore » determine the effect of neutron radiation environment on the RIS-GB structure dependence. This investigation found the relationship between GB structure and RIS is also active for F/M steels irradiated using neutrons. The data generated from the neutron irradiation is also compared to RIS data generated using proton irradiations on the same heat of model alloy.« less
  • Ferritic/Martensitic (F/M) steels with high Cr content posses the high temperature strength and low swelling rates required for advanced nuclear reactor designs. Radiation induced segregation (RIS) occurs in F/M steels due to solute atoms preferentially coupling to point defect fluxes which migrate to defect sinks, such as grain boundaries (GBs). The RIS response of F/M steels and austenitic steels has been shown to be dependent on the local structure of GBs where low energy structures have suppressed RIS responses. This relationship between local GB structure and RIS has been demonstrated primarily in ion-irradiated specimens. A 9 wt.% Cr model alloymore » steel was irradiated to 3 dpa using neutrons at the Advanced Test Reactor (ATR) to determine the effect of a neutron radiation environment on the RIS response at different GB structures. This investigation found the relationship between GB structure and RIS is also active for F/M steels irradiated using neutrons. The data generated from the neutron irradiation is also compared to RIS data generated using proton irradiations on the same heat of model alloy.« less
  • Reduced activation ferritic/martensitic steels (RAFs) are leading candidates for blanket and first wall of fusion reactors where effects of displacement damage and helium production are important subjects to be investigated. To obtain systematic and accurate information of microstructural response under fusion environment, dual-ion irradiation method was applied. In order to estimate the microstructural response under fusion neutron irradiation environment, ion-beam irradiation was carried out with helium and metallic self ions. The study is focused on JLF-1 single- and dial-ion irradiated up to 60 dpa at 693, 743 and 793 K. The damage rate and helium injection rate were 1.0 xmore » 10{sup -3} dpa/sec and 15 x 10{sup -3} appm He/sec. At 743 K, void cavity structure was observed under dual-ion irradiation where the contribution of void structure on hardening was not so significant. Irradiation hardening and swelling were depended for the case of dual-ion irradiation. It is attempted to quantitatively relate the dislocation and cavities to the irradiation induced hardening.« less