Gas leak tightness of SiC/SiC composites at elevated temperature
- 1. Graduate School of Engineering, Muroran Institute of Technology, Muroran, Hokkaido (Japan)
- 2. OASIS, Muroran Institute of Technology, Muroran, Hokkaido (Japan)
Description
Highlights: • NITE-SiC/SiC has extremely densified microstructure compared with other SiC/SiC composite like CVI. • Excellent helium and hydrogen gas-leak tightness of SiC/SiC composites by DEMO-NITE method from prototype industrialization production line was presented. • The excellence against stainless steel and Zircaloy at elevated temperature, together with generic excellent properties of SiC will be inevitable for innovative blanket and divertors for DEMO- and power- fusion reactors. - Abstract: SiC/SiC composite materials are attractive candidates for high heat flux components and blanket of fusion reactor, mainly due to their high temperature properties, radiation damage tolerance and low induced radioactivity. One of the challenges for SiC/SiC application in fusion reactors is to satisfy sufficient gas leak tightness of hydrogen and helium isotopes. Although many efforts have been carried-out, SiC/SiC composites by conventional processes have not been successful to satisfy the requirements, except SiC/SiC composites by NITE-methods. Toward the early realization of SiC/SiC components into fusion reactor systems process development of NITE-process has been continued. Followed to the brief introduction of recently developed DEMO-NITE process, baseline properties and hydrogen and helium gas leak tightness is presented. SiC/SiC claddings with 10 mm in diameter and 1 mm in wall thickness are tested by gas leak tightness system developed. The leak tightness measurements are done room temperature to 400 °C. Excellent gas leak tightness equivalent or superior to Zircaloy claddings for light water fission reactors is confirmed. The excellent gas leak tightness suggests nearly perfect suppression of large gas leak path in DEMO-NITE SiC/SiC.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2015.11.044Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2015.11.044;
- PII
- S0920-3796(15)30375-6;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 109-111
- Journal Issue
- Part B
- Journal Page Range
- p. 1498-1501
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 12. international symposium on fusion nuclear technology
- Acronym
- ISFNT-12
- Dates
- 14-18 Sep 2015
- Place
- Jeju Island (Korea, Republic of)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48067948
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; COMPOSITE MATERIALS; DEMONSTRATION PLANTS; DIVERTORS; HEAT FLUX; HELIUM; HELIUM ISOTOPES; HYDROGEN; LEAKS; MICROSTRUCTURE; RADIATION EFFECTS; RADIOACTIVITY; SILICON CARBIDES; STAINLESS STEELS; TEMPERATURE RANGE 0400-1000 K; THERMONUCLEAR REACTORS; TOLERANCE; WALLS; WATER; ZIRCALOY
- Descriptors DEC
- ALLOYS; CARBIDES; CARBON ADDITIONS; CARBON COMPOUNDS; DEPOSITION; ELEMENTS; FLUIDS; GASES; HIGH ALLOY STEELS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; ISOTOPES; MATERIALS; NONMETALS; OXYGEN COMPOUNDS; RARE GASES; SILICON COMPOUNDS; STEELS; SURFACE COATING; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Copyright
- Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.