Progress in the U.S./Japan PHENIX Project for the Technological Assessment of Plasma Facing Components for DEMO Reactors. (3rd October 2017)
- Record Type:
- Journal Article
- Title:
- Progress in the U.S./Japan PHENIX Project for the Technological Assessment of Plasma Facing Components for DEMO Reactors. (3rd October 2017)
- Main Title:
- Progress in the U.S./Japan PHENIX Project for the Technological Assessment of Plasma Facing Components for DEMO Reactors
- Authors:
- Katoh, Yutai
Clark, Daniel
Ueda, Yoshio
Hatano, Yuji
Yoda, Minami
Sabau, Adrian S.
Yokomine, Takehiko
Garrison, Lauren M.
Geringer, J. Wilna
Hasegawa, Akira
Hinoki, Tatsuya
Shimada, Masashi
Buchenauer, Dean
Oya, Yasuhisa
Muroga, Takeo - Abstract:
- Abstract: The PHENIX Project is a 6-year U.S./Japan bilateral, multi-institutional collaboration program for the Technological Assessment of Plasma Facing Components for DEMO Reactors. The goal is to address the technical feasibility of helium-cooled divertor concepts using tungsten as the armor material in fusion power reactors. The project specifically attempts to (1) improve heat transfer modeling for helium-cooled divertor systems through experiments including steady-state and pulsed high-heat-load testing, (2) understand the thermomechanical properties of tungsten metals and alloys under divertor-relevant neutron irradiation conditions, and (3) determine the behavior of tritium in tungsten materials through high-flux plasma exposure experiments. The High Flux Isotope Reactor and the Plasma Arc Lamp facility at Oak Ridge National Laboratory, the Tritium Plasma Experiment facility at Idaho National Laboratory, and the helium loop at Georgia Institute of Technology are utilized for evaluation of the response to high heat loads and tritium interactions of irradiated and unirradiated materials and components. This paper provides an overview of the progress achieved during the first 3 years and discusses the plan for the remainder of the project.
- Is Part Of:
- Fusion science and technology. Volume 72:Number 3(2017)
- Journal:
- Fusion science and technology
- Issue:
- Volume 72:Number 3(2017)
- Issue Display:
- Volume 72, Issue 3 (2017)
- Year:
- 2017
- Volume:
- 72
- Issue:
- 3
- Issue Sort Value:
- 2017-0072-0003-0000
- Page Start:
- 222
- Page End:
- 232
- Publication Date:
- 2017-10-03
- Subjects:
- Plasma facing components -- helium-cooled divertor -- tungsten armor
Fusion reactors -- Periodicals
Nuclear fusion -- Periodicals
Fusion reactors
Nuclear fusion
Periodicals
621.48405 - Journal URLs:
- http://www.tandfonline.com/ ↗
- DOI:
- 10.1080/15361055.2017.1333868 ↗
- Languages:
- English
- ISSNs:
- 1536-1055
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 7049.xml