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Materials technology for an advanced space power nuclear reactor concept: program summary
| Content Provider | NASA Technical Reports Server (NTRS) |
|---|---|
| Author | Gluyas, R. E. Watson, G. K. |
| Copyright Year | 1975 |
| Description | The results of a materials technology program for a long-life (50,000 hr), high-temperature (950 C coolant outlet), lithium-cooled, nuclear space power reactor concept are reviewed and discussed. Fabrication methods and compatibility and property data were developed for candidate materials for fuel pins and, to a lesser extent, for potential control systems, reflectors, reactor vessel and piping, and other reactor structural materials. The effects of selected materials variables on fuel pin irradiation performance were determined. The most promising materials for fuel pins were found to be 85 percent dense uranium mononitride (UN) fuel clad with tungsten-lined T-111 (Ta-8W-2Hf). |
| File Size | 3037401 |
| Page Count | 57 |
| File Format | |
| Alternate Webpage(s) | http://archive.org/details/NASA_NTRS_Archive_19750010330 |
| Archival Resource Key | ark:/13960/t0fv3bm75 |
| Language | English |
| Publisher Date | 1975-03-01 |
| Access Restriction | Open |
| Subject Keyword | Metallic Materials Nitrides Tantalum Alloys Nuclear Fuel Elements Uranium Compounds Irradiation Lithium Space Power Reactors Ntrs Nasa Technical Reports Server (ntrs) Nasa Technical Reports Server Aerodynamics Aircraft Aerospace Engineering Aerospace Aeronautic Space Science |
| Content Type | Text |
| Resource Type | Technical Report |
