Neutron irradiation effects on the mechanical properties of powder metallurgical processed tungsten alloys

Takeshi Miyazawa; Lauren M. Garrison; Josina W. Geringer; Makoto Fukuda; Yutai Katoh; Tatsuya Hinoki; Akira Hasegawa

doi:10.1016/j.jnucmat.2019.151910

Neutron irradiation effects on the mechanical properties of powder metallurgical processed tungsten alloys

Takeshi Miyazawa, Lauren M. Garrison, Josina W. Geringer, Makoto Fukuda, Yutai Katoh, Tatsuya Hinoki, Akira Hasegawa

Research output: Contribution to journal › Article › peer-review

33 Scopus citations

Abstract

Neutron irradiation effects on the tensile properties of Pure W, K-doped W, W–3%Re, and K-doped W–3%Re were examined under the US-Japan collaboration project PHENIX. The fission neutron irradiation experiments were carried out up to 0.74 dpa at 600 °C and 800 °C. Pure W (SR) showed irradiation hardening and loss of ductility after irradiation at 600 °C and 800 °C. K-doped W–3%Re (SR) also exhibited irradiation hardening but was ductile after irradiation. Characteristic points of the K-doped W–3%Re (SR) are small grain size and layered structure. The stress-relief treatment and the layered structure may improve the ductility of powder-metallurgy W alloys after neutron irradiation, so a combination of K-doping and Re addition would be beneficial to improve irradiation resistance.

Original language	English
Article number	151910
Journal	Journal of Nuclear Materials
Volume	529
DOIs	https://doi.org/10.1016/j.jnucmat.2019.151910
State	Published - Feb 2020

Funding

The authors thank M. McAlister for technical support in the tensile tests. This work was performed as part of the U.S.–Japan PHENIX Collaboration Project on Technological Assessment of Plasma Facing Components for DEMO Reactors. ORNL research was sponsored by the U.S. Department of Energy, Office of Fusion Energy Sciences , under contract DE-AC05-00OR22725 with UT-Battelle, LLC. This study was supported by JSPS KAKENHI , Grant Number 17H01364 . Appendix A The authors thank M. McAlister for technical support in the tensile tests. This work was performed as part of the U.S.?Japan PHENIX Collaboration Project on Technological Assessment of Plasma Facing Components for DEMO Reactors. ORNL research was sponsored by the U.S. Department of Energy, Office of Fusion Energy Sciences, under contract DE-AC05-00OR22725 with UT-Battelle, LLC. This study was supported by JSPS KAKENHI, Grant Number 17H01364.

Funders	Funder number
Office of Fusion Energy Sciences	DE-AC05-00OR22725 with UT-Battelle
U.S. Department of Energy
Fusion Energy Sciences	DE-AC05-00OR22725
Oak Ridge National Laboratory
Japan Society for the Promotion of Science	17H01364

Keywords

Neutron irradiation
Polycrystalline
Tensile properties
Thermal neutron shield
Tungsten

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10.1016/j.jnucmat.2019.151910

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title = "Neutron irradiation effects on the mechanical properties of powder metallurgical processed tungsten alloys",

abstract = "Neutron irradiation effects on the tensile properties of Pure W, K-doped W, W–3%Re, and K-doped W–3%Re were examined under the US-Japan collaboration project PHENIX. The fission neutron irradiation experiments were carried out up to 0.74 dpa at 600 °C and 800 °C. Pure W (SR) showed irradiation hardening and loss of ductility after irradiation at 600 °C and 800 °C. K-doped W–3%Re (SR) also exhibited irradiation hardening but was ductile after irradiation. Characteristic points of the K-doped W–3%Re (SR) are small grain size and layered structure. The stress-relief treatment and the layered structure may improve the ductility of powder-metallurgy W alloys after neutron irradiation, so a combination of K-doping and Re addition would be beneficial to improve irradiation resistance.",

keywords = "Neutron irradiation, Polycrystalline, Tensile properties, Thermal neutron shield, Tungsten",

author = "Takeshi Miyazawa and Garrison, {Lauren M.} and Geringer, {Josina W.} and Makoto Fukuda and Yutai Katoh and Tatsuya Hinoki and Akira Hasegawa",

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AU - Miyazawa, Takeshi

AU - Garrison, Lauren M.

AU - Geringer, Josina W.

AU - Fukuda, Makoto

AU - Katoh, Yutai

AU - Hinoki, Tatsuya

AU - Hasegawa, Akira

PY - 2020/2

Y1 - 2020/2

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AB - Neutron irradiation effects on the tensile properties of Pure W, K-doped W, W–3%Re, and K-doped W–3%Re were examined under the US-Japan collaboration project PHENIX. The fission neutron irradiation experiments were carried out up to 0.74 dpa at 600 °C and 800 °C. Pure W (SR) showed irradiation hardening and loss of ductility after irradiation at 600 °C and 800 °C. K-doped W–3%Re (SR) also exhibited irradiation hardening but was ductile after irradiation. Characteristic points of the K-doped W–3%Re (SR) are small grain size and layered structure. The stress-relief treatment and the layered structure may improve the ductility of powder-metallurgy W alloys after neutron irradiation, so a combination of K-doping and Re addition would be beneficial to improve irradiation resistance.

KW - Neutron irradiation

KW - Polycrystalline

KW - Tensile properties

KW - Thermal neutron shield

KW - Tungsten

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Neutron irradiation effects on the mechanical properties of powder metallurgical processed tungsten alloys

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Keywords

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