Process and device for measuring the local thermal power in a nuclear reactor
US4634570A · kind A · utility
Assignee
Inventors
Key dates
| Filing date | Jul 5, 1983 |
| Grant date | Jan 6, 1987 |
| Priority date | — |
| Expiry date | Jul 5, 2003 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY02E30/30
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
This device is intended to measure the thermal power released locally in an area of the core of a nuclear reactor and comprises a conduit in the core of the reactor from the outside which contains a body which absorbs gamma radiations located at the measuring area and associated with a measuring thermocouple. A first junction of the thermocouple is placed so that it is brought to a temperature essentially representative of that of the reactor coolant and slightly affected by the gamma flux, and a second junction is placed so that it is brought to a temperature representative of that of the body which absorbs the radiations. The device comprises a supplementary thermocouple which has a first junction located near that of the measuring thermocouple and a second junction brought to a reference temperature. The output signals of the two thermocouples are applied to means which permit an automatic correction of the indications supplied by the measuring thermocouple as a function of the variations of the output signal of the supplementary thermocouple.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.