Low Temperature Fatigue Properties of Advanced Cyanate-Ester Blends after Reactor Irradiation
- Atomic Institute of the Austrian Universities, 1020 Vienna (Austria)
- Composite Technology Development Inc., Lafayette, CO (United States)
Fiber reinforced composites offer a broad spectrum of applications due to their excellent material performance under demanding conditions. Therefore, these materials will also be employed as insulation systems for the superconducting magnets in fusion devices. However, high doses of gamma and neutron irradiation lead to a drastic damage mostly of the organic matrices, such as pure epoxy resins. An improvement of these composites with regard to higher radiation resistance is of special importance to ensure stable coil operation over the plant lifetime. Recently, a series of advanced S2-glass fiber composites was developed, which consist of novel cyanate ester (CE) blends. All systems were irradiated in the TRIGA reactor (Vienna, Austria) to a neutron fluence of 1x1021 and 1x1022 m-2 (E>0.1 MeV), in order to assess the radiation hardness of their ultimate tensile strength. Furthermore, the material performance under cyclic load was investigated by tension-tension fatigue measurements at 77 K in view of the pulsed ITER operating conditions.
- OSTI ID:
- 20653214
- Journal Information:
- AIP Conference Proceedings, Vol. 711, Issue 1; Conference: CEC 2003: Cryogenic engineering and international cryogenic materials conference on advances in cryogenic engineering, Anchorage, AK (United States), 22-26 Sep 2003; Other Information: DOI: 10.1063/1.1774572; (c) 2004 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
COMPOSITE MATERIALS
CYANATES
EPOXIDES
ESTERS
FATIGUE
FIBERS
HARDNESS
IRRADIATION
ITER TOKAMAK
KEV RANGE 100-1000
LIFETIME
NEUTRON FLUENCE
NEUTRONS
PHYSICAL RADIATION EFFECTS
REINFORCED MATERIALS
RESINS
SUPERCONDUCTING MAGNETS
TEMPERATURE RANGE 0065-0273 K
TENSILE PROPERTIES
TRIGA-2-VIENNA REACTOR