PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron–Shielded Irradiated Tungsten
Abstract
The United States and Japan have collaborated on fusion materials research in a series of agreements reaching back to 1981. The PHENIX collaboration is the latest U.S.-Japan project which spans 2013 to 2019 and has the goal of assessing technical feasibility of tungsten-based, helium-cooled plasma-facing component concepts for a demonstration fusion power reactor (DEMO). Task 2 within the PHENIX project is focused on evaluating the neutron irradiation effects in tungsten. For tungsten, the transmutation to Re and Os is at least as important to determining its properties after irradiation as the displacement damage, and the transmutation rate depends on the energy spectrum of the reactor. A large-scale, instrumented irradiation capsule with thermal neutron shielding to better mimic fusion conditions was irradiated in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory. The tungsten specimens were irradiated in different temperature zones between 500°C and 1200°C to doses of ~0.2 to 0.7 displacements per atom. More than 20 varieties of pure tungsten and tungsten alloys were included in the irradiation, and they were evaluated in the 3025E hot-cell facility and at the Low Activation Materials Development and Analysis Laboratory. The elevated temperature tensile, fracture toughness, hardness, thermal conductivity, electrical resistivity,more »
- Authors:
-
[1];
[1];
[1];
[1];
[1];
[1];
[1];
[1]
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Osaka Prefecture Univ., Sakai (Japan)
- Tohoku Univ., Sendai (Japan)
- Kyoto Univ., Kyoto (Japan)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Illinois at Urbana-Champaign, Urbana, IL (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC)
- OSTI Identifier:
- 1560489
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Fusion Science and Technology
- Additional Journal Information:
- Journal Volume: 75; Journal Issue: 6; Journal ID: ISSN 1536-1055
- Publisher:
- American Nuclear Society
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; neutron irradiation; tungsten; divertor; mechanical properties; fusion materials
Citation Formats
Garrison, Lauren M., Katoh, Yutai, Geringer, Josina Wilna, Akiyoshi, Masafumi, Chen, Xiang, Fukuda, Makoto, Hasegawa, Akira, Hinoki, Tatsuya, Hu, Xunxiang, Koyanagi, Takaaki, Lang, Eric, McAlister, Michael, McDuffee, Joel Lee, Miyazawa, Takeshi, Parish, Chad M., Proehl, Emily, Reid, Nathan, Robertson, Janet, and Wang, Hsin. PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron–Shielded Irradiated Tungsten. United States: N. p., 2019.
Web. doi:10.1080/15361055.2019.1602390.
Garrison, Lauren M., Katoh, Yutai, Geringer, Josina Wilna, Akiyoshi, Masafumi, Chen, Xiang, Fukuda, Makoto, Hasegawa, Akira, Hinoki, Tatsuya, Hu, Xunxiang, Koyanagi, Takaaki, Lang, Eric, McAlister, Michael, McDuffee, Joel Lee, Miyazawa, Takeshi, Parish, Chad M., Proehl, Emily, Reid, Nathan, Robertson, Janet, & Wang, Hsin. PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron–Shielded Irradiated Tungsten. United States. https://doi.org/10.1080/15361055.2019.1602390
Garrison, Lauren M., Katoh, Yutai, Geringer, Josina Wilna, Akiyoshi, Masafumi, Chen, Xiang, Fukuda, Makoto, Hasegawa, Akira, Hinoki, Tatsuya, Hu, Xunxiang, Koyanagi, Takaaki, Lang, Eric, McAlister, Michael, McDuffee, Joel Lee, Miyazawa, Takeshi, Parish, Chad M., Proehl, Emily, Reid, Nathan, Robertson, Janet, and Wang, Hsin. Mon .
"PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron–Shielded Irradiated Tungsten". United States. https://doi.org/10.1080/15361055.2019.1602390. https://www.osti.gov/servlets/purl/1560489.
@article{osti_1560489,
title = {PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron–Shielded Irradiated Tungsten},
author = {Garrison, Lauren M. and Katoh, Yutai and Geringer, Josina Wilna and Akiyoshi, Masafumi and Chen, Xiang and Fukuda, Makoto and Hasegawa, Akira and Hinoki, Tatsuya and Hu, Xunxiang and Koyanagi, Takaaki and Lang, Eric and McAlister, Michael and McDuffee, Joel Lee and Miyazawa, Takeshi and Parish, Chad M. and Proehl, Emily and Reid, Nathan and Robertson, Janet and Wang, Hsin},
abstractNote = {The United States and Japan have collaborated on fusion materials research in a series of agreements reaching back to 1981. The PHENIX collaboration is the latest U.S.-Japan project which spans 2013 to 2019 and has the goal of assessing technical feasibility of tungsten-based, helium-cooled plasma-facing component concepts for a demonstration fusion power reactor (DEMO). Task 2 within the PHENIX project is focused on evaluating the neutron irradiation effects in tungsten. For tungsten, the transmutation to Re and Os is at least as important to determining its properties after irradiation as the displacement damage, and the transmutation rate depends on the energy spectrum of the reactor. A large-scale, instrumented irradiation capsule with thermal neutron shielding to better mimic fusion conditions was irradiated in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory. The tungsten specimens were irradiated in different temperature zones between 500°C and 1200°C to doses of ~0.2 to 0.7 displacements per atom. More than 20 varieties of pure tungsten and tungsten alloys were included in the irradiation, and they were evaluated in the 3025E hot-cell facility and at the Low Activation Materials Development and Analysis Laboratory. The elevated temperature tensile, fracture toughness, hardness, thermal conductivity, electrical resistivity, density, elemental composition, and microstructure properties of the irradiated materials are being collected. Furthermore, this paper overviews the experimental design, specimen matrix, and the initial results of postirradiation examinations.},
doi = {10.1080/15361055.2019.1602390},
journal = {Fusion Science and Technology},
number = 6,
volume = 75,
place = {United States},
year = {Mon May 20 00:00:00 EDT 2019},
month = {Mon May 20 00:00:00 EDT 2019}
}
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Works referencing / citing this record:
Pre-Irradiation Comparison of W-Based Alloys for the PHENIX Campaign: Microstructure, Composition, and Mechanical Properties
journal, May 2019
- Lang, Eric; Reid, Nathan; Garrison, Lauren
- Fusion Science and Technology, Vol. 75, Issue 6