Method for measuring lanthanide content dissolved in uranium oxide
US7094608B2 · kind B2 · utility
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4Claims
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Key dates
| Filing date | Nov 27, 2002 |
| Grant date | Aug 22, 2006 |
| Priority date | — |
| Expiry date | Jul 1, 2024 |
Classification
- Technology area (CPC C)Chemistry; Metallurgy
- CPC primaryC01P2006/80
- WIPO fieldMeasurement
- WIPO sectorInstruments
Abstract
The present invention relates to a method for measuring the content of Lanthanides dissolved in uranium oxide, wherein the Lanthanides content in the nuclear fuel pellet is measured using the thermo gravimetric analysis which measures the weight variation caused by the oxidation and heat treatment of the nuclear fuel pellet. This method provides an advantage in that the Lanthanide content can be measured using relatively simple equipments such as an electric furnace and a balance.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.