The Use of Basalt, Basalt Fibers and Modified Graphite for Nuclear Waste Repository - 12150
- Institute for Nuclear Research, pr. Nauky 47, Kyiv, 03680 (Ukraine)
- HHK Technologies, 3535 Wilcreast Dr., Houston TX 77042 (United States)
New materials enhancing the isolation of radioactive waste and spent nuclear fuel are continuously being developed.. Our research suggests that basalt-based materials, including basalt roving chopped basalt fiber strands, basalt composite rebar and materials based on modified graphite, could be used for enhancing radioactive waste isolation during the storage and disposal phases and maintaining it during a significant portion of the post-closure phase. The basalt vitrification process of nuclear waste is a viable alternative to glass vitrification. Basalt roving, chopped basalt fiber strands and basalt composite rebars can significantly increase the strength and safety characteristics of nuclear waste and spent nuclear fuel storages. Materials based on MG are optimal waterproofing materials for nuclear waste containers. (authors)
- Research Organization:
- WM Symposia, 1628 E. Southern Avenue, Suite 9-332, Tempe, AZ 85282 (United States)
- OSTI ID:
- 22293456
- Report Number(s):
- INIS-US-14-WM-12150; TRN: US14V1110114980
- Resource Relation:
- Conference: WM2012: Waste Management 2012 conference on improving the future in waste management, Phoenix, AZ (United States), 26 Feb - 1 Mar 2012; Other Information: Country of input: France; 13 refs.
- Country of Publication:
- United States
- Language:
- English
Similar Records
Hydrothermal interactions of cesium and strontium phases from spent unreprocessed fuel with basalt phases and basalts
Feasibility assessment of copper-base waste package container materials in nuclear waste repositories sited in basalt and tuff