Nuclear fuel pellet-cladding interaction test device and method modeling in-core reactor thermal conditions
US4643866A · kind A · utility
6Cited by
9References
24Claims
0Family size
Assignee
Inventors
Key dates
| Filing date | Aug 24, 1983 |
| Grant date | Feb 17, 1987 |
| Priority date | — |
| Expiry date | Aug 24, 2003 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY02E30/30
- WIPO fieldThermal processes and apparatus
- WIPO sectorMechanical engineering
Abstract
A method and apparatus for testing characteristics of nuclear fuel pellet interaction with nuclear reactor fuel rod cladding whereby the temperature profile within a nuclear fuel rod is more closely modeled in the test device than in the prior art discloses the use of high frequency microwave radiation to heat the fuel pellets within the cladding and using the cladding itself as a waveguide. Sensors monitor various operating parameters and a water jacket cools the test cladding.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.