Measurement of the volumetric activity of gamma-emitting radionuclides in process liquids in nuclear facilities.
Nuclear Facilities
Waste Management
Key Features
Measurement of volumetric activity of gammaemitting radionuclides in process liquids in nuclear facilities
Suitable for high temperatures
Monitor type ATL - monitor detector is attached to the measured pipeline
Optionally can provide safety classified function, category C, according to the EN 61226 standard
In-built Cs-137 check source
Description
The monitor is intended for the measurement of volumetric activity of gamma radionuclides in liquids such as process waters in nuclear facilities during routine, accident and post-accident conditions.
The monitor assembly is composed of:
gamma detector, including high temperature gamma scintillator NaI(Tl) Ø 1“ × 1 “,
10 mm thick lead collimator,
check and stabilization source Cs-137 with the activity of 16 kBq,
radiation processing unit RPU-04 with a 1024- channel analyser for the processing of data from the detector.
en
cz
