The Gamma spectrometry laboratory of the Nuclear Security Department is equipped with a wide range of gamma detectors for diverse use:
- HPGe (high-purity germanium) detectors for precise qualitative and quantitative analysis of radioactive and nuclear materials (coaxial, planar and well-type for special uses)
- LaBr3 scintillation detectors capable of handling higher intensity radiation fields
- Compact CZT (CdZnTe) detectors for hard-to-reach measurement positions
- Most of the available gamma detectors can be used in-field. Providing expert scientific analysis and on-site measurement support is essential for the in-field nuclear forensic examination of materials found outside of regulatory control or collected at a radiological crime scene. In-field measurements are also useful for in-situ industrial analysis, e.g. at Paks NPP. The gamma team contributes to various national and international nuclear security and safeguards projects (see Reference Projects below).
Using the available expertise and equipment the following measurements can be provided:
- Determination of gamma emitting radioactive isotope composition and activity
- Determination of isotopic composition and quantitative measurement of uranium containing materials
- Uranium age dating (time elapsed since the last chemical separation) and determination of reprocessed character
- Quantitative analysis of thorium containing materials
- Plutonium identification, isotopic composition analysis, and quantitative analysis
Reference Projects:
- In-field and laboratory measurements of confiscated nuclear and radioactive samples
- Paks NPP: Nuclear content determination after re-capsulating of damaged spent fuel assemblies
- Paks NPP: Burnup measurement and irradiation history validation of spent fuel assemblies
- Paks NPP: Verification of U-enrichment in fresh fuel assemblies
- Paks NPP: Measurement of (radioactive) corrosion products in the primary and auxiliary (CVCS) circuits
- Determining isotope composition of radioactive waste
- Helping in reducing radioactive waste during decommissioning
- IPNDV: Nuclear disarmament verification
- Participation in international exercises: ITWG CMX nuclear forensics exercises
Measurement of a calibration source with 2 HPGe detectors (planar and coaxial) in the Gamma laboratory
Nuclear material detection in MOX – mixed oxide fuel –fuel by using planar HPGe detector (MOL, Belgium)
Verification of U-enrichment in fresh fuel assembly by using LaBr3 (above) and HPGe (foreground) detectors (Paks NPP)
Efficiency calibration of an HPGe detector with a mock-up assembly model built with fuel pins similar to the fuel used at Paks NPP
Identification of unknown radioactive/nuclear material using on-site gamma spectrometry; Radiological Crime Scene Management demonstration at the IAEA Regional Training Course on Practical Introduction to Nuclear Forensics
Low background iron chamber and a well-type HPGe detector at the NSD
