Gamma spectrometry is the main method used by nuclear safeguards inspectors for fast in-field verification of uranium and plutonium. It is a non-destructive method, which enables swift determinations of the uranium enrichment and of plutonium isotopic composition in field.
Examples of the JRC contributions to the improvement of this method include isotopic analysis of shielded nuclear material, evaluating influence of bismuth on uranium measurements, validation of spectrum analysis for European mixed-oxide (MOX), medium-resolution gamma spectrometry (MRGS) and a large free spectrum database.
Isotopic analysis of shielded material
The JRC-Karlsruhe tested the FRAM software's ability to accurately determine the isotopic composition of shielded uranium and plutonium. Over 17 000 spectra of certified reference materials were analysed using different FRAM parameter sets. The performance of FRAM was evaluated based on shielding thickness, measurement time, isotopic composition, and spectrum quality.
For uranium analysis, a new FRAM parameter set was developed, providing more accurate results than the default sets. For plutonium the default parameter sets were found to be optimal. As nuclear material is frequently stored in shielded containers, these results are relevant for the daily work of nuclear safeguards inspectors in the field. More on the ESARDA Bulletin n. 60

Bismuth and isotopic analysis of uranium
The X-ray fluorescence (XRF) peaks of bismuth impact the determination of 235U enrichment by gamma spectrometry. Figure shows the overlapping peaks. These XRF peaks are present in most spectra recorded by germanium detectors built after 2003, due to bismuth in the new detectors, and in spectra of reprocessed uranium and of some cladded uranium fuel, due to bismuth in these materials.
The JRC-Karlsruhe found that bismuth in the detector causes a bias of about 3% in the measured 235U enrichment. If bismuth cannot be avoided, bias correction or increased reported uncertainty should be considered. Detector manufacturers were informed and already provided bismuth-free detectors for safeguards. More in JNMM Volume 50, Issue 1

Medium resolution gamma spectrometry
MRGS is increasingly used for in-field nuclear safeguards measurements due to its portability and ease of maintenance. However, there is still room for improvement in related spectra analysis software.
The JRC-Karlsruhe collected high-quality medium-resolution spectra of certified uranium and plutonium reference materials using CdZnTe and LaBr3 detectors, in collaboration with the IAEA. These spectra are crucial for developing and validating spectrum analysis algorithms.

Isotopic analysis of European MOX fuel
All routinely used software for plutonium isotopic analysis has been developed outside Europe and has been validated for non-European plutonium. However, the plutonium in European MOX fuel, with its high burn-up level, is unique. Therefore, the JRC and its international partners fine-tuned and tested the software for European plutonium. This is a key element for trustworthy nuclear safeguards in Europe.
A free spectrum database
The JRC-Karlsruhe recorded around 20 000 spectra of certified reference materials for research topics on gamma spectrometry, using high-resolution and medium resolution gamma spectrometers. All spectra are freely available through the JRC Data Catalogue. To extend the free spectrum database, the JRC-Karlsruhe will use validated open source modelling and simulation tools to generate artificial spectra, representing a wide range of material compositions and experimental setups.