The challenge of developing structural materials for fusion power systems
Open Access
- 1 October 1998
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 258-263, 7-17
- https://doi.org/10.1016/s0022-3115(98)00352-3
Abstract
No abstract availableKeywords
This publication has 32 references indexed in Scilit:
- The effect of irradiation on the stability and properties of monolithic silicon carbide and SiCf/SiC composites up to 25 dpaJournal of Nuclear Materials, 1995
- Embrittlement of CrMo steels after low fluence irradiation in HFIRJournal of Nuclear Materials, 1995
- Response of unirradiated and neutron-irradiated vanadium alloys to Charpy-impact loadingJournal of Nuclear Materials, 1991
- Some radiological limitations on the compositions of low-activation materials for power reactorsJournal of Nuclear Materials, 1988
- Development of ferritic steels for reduced activation: The US programJournal of Nuclear Materials, 1986
- Tensile properties and microstructure of helium injected and reactor irradiateD V-20 TiJournal of Nuclear Materials, 1981
- Neutron irradiation-induced voids in β-silicon carbideJournal of Nuclear Materials, 1973
- Thermal conductivity of neutron-irradiated pyrolytic β-silicon carbideJournal of Nuclear Materials, 1973
- The expansion of silicon carbide by neutron irradiation at high temperatureJournal of Nuclear Materials, 1971
- Effects of fast-neutron irradiation on pyrolytic silicon carbideJournal of Nuclear Materials, 1969