658 research outputs found

    Gamma ray emission imaging in the medical and nuclear safeguards fields

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    Gamma rays emitted from within an object can reveal information about that object in a non-destructive way, i.e. without physically opening the object and looking inside. This makes gamma ray emission imaging very useful in widely varying applications. In these notes, we highlight its application to the medical field, where we discuss molecular imaging in nuclear medicine and in vivo dose delivery verification in particle beam radiotherapy, and nuclear safeguards field, where imaging of spent nuclear fuel assemblies is part of monitoring the non-proliferation of nuclear weapons. The purpose and basic principles of gamma ray emission imaging are discussed as the foundation to look in more detail into the essential instrument design considerations and the iterative image reconstruction procedures. These notes are not intended to be a comprehensive review; their purpose is to introduce gamma ray emission imaging to those that are new to this technique. The examples of implementation that are presented were thus chosen in order to introduce the reader to a fairly wide range of applications and practical implementations

    New developments in TRI mu P and RIASH at KVI

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    The status of the TRI mu P facility at KVI is reviewed. Recent results on ion catcher devices are described. A thermo-ionizer for use with alkali and earth-alkali elements is close to completion. Concerning the use of superfluid helium as stopping medium, evidence that second sound pulses can be used to extract ions from the helium surface has been obtained. Based on the observation of highly efficient ion transport in helium, neon and argon gas below about 100 K, we propose the operation of noble gas ion catchers at cryogenic temperatures.</p

    Next-generation sequencing in clinical practice

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    During the past few decades, Sanger sequencing represented the “gold standard” technique. In order to better define the mutational status of several genes at the same time, next-generation sequencing methodologies have been introduced in the molecular laboratory workflow. In the era of personalized medicine, this technological improvement plays a key role in the comprehensive molecular characterization of cancer patients in order to get a “tile” target therapy. For different cancer patients, different target therapies are available and different genes serve as clinical it relevant biomarkers. This chapter reviews the principal features of these novel technologies and their application on different biological specimens, in the light of biomarkers analysis to select cancer patients for target therapies

    New developments in TRImP and RIASH at KVI

    No full text
    The status of the TRI mu P facility at KVI is reviewed. Recent results on ion catcher devices are described. A thermo-ionizer for use with alkali and earth-alkali elements is close to completion. Concerning the use of superfluid helium as stopping medium, evidence that second sound pulses can be used to extract ions from the helium surface has been obtained. Based on the observation of highly efficient ion transport in helium, neon and argon gas below about 100 K, we propose the operation of noble gas ion catchers at cryogenic temperatures.</p

    Fuel rod classification from Passive Gamma Emission Tomography (PGET) of spent nuclear fuel assemblies

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    Safeguarding the disposal of spent nuclear fuel in a geological repository needs an effective, efficient, reliable and robust non-destructive assay (NDA) system to ensure the integrity of the fuel prior to disposal. In the context of the Finnish geological repository, Passive Gamma Emission Tomography (PGET) will be a part of such an NDA system. We report here on the results of PGET measurements at the Finnish nuclear power plants during the years 2017-2020. The PGET prototype device developed by IAEA and partners was used during 2017- 2019, whereas an updated device was used in 2020. The PGET device contains two linear arrays of collimated CdZnTe (CZT) gamma ray detectors installed opposite each other inside a torus. Gamma activity profiles are recorded from all angles by rotating the detector arrays around the fuel assembly that has been inserted into the center of the torus. Image reconstruction from the resulting tomographic data is defined as a constrained minimization problem with the function being minimized containing a data fidelity term and regularization terms. The activity and attenuation maps, as well as detector sensitivity corrections, are the variables in the minimization process. The regularization terms ensure that prior information on the (possible) locations of fuel rods and their diameter are taken into account. Fuel rod classification, the main purpose of the PGET method, is based on the difference of the activity of a fuel rod from its immediate neighbors, taking into account its distance from the assembly center. The classification is carried out by a support vector machine. We report on the results for 10 different fuel types with burnups between 5.72 and 55.0 GWd/tU, cooling times between 1.87 and 34.6 years and initial enrichments between 1.9 and 4.4%. For the 77 fuel assemblies measured, the total misclassification rate including misclassifications of missing fuel rods, present rods and water channels, was 0.94% for the Olkiluoto campaigns and 0.66% for the Loviisa campaigns. Further development of the image reconstruction method is discussed. We conclude that the combination of the PGET device and our image reconstruction method provides a reliable base for fuel rod classification. The method is well-suited for nuclear safeguards verification of BWR fuel assemblies in Finland prior to geological disposal. For VVER-440 assemblies, some further work is needed to investigate the ability to detect missing rods near the center of the assembly

    In-air and in-water performance comparison of Passive Gamma Emission Tomography with activated Co-60 rods

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    A first‐of‐a‐kind geological repository for spent nuclear fuel is being built in Finland and will soon start operations. To make sure all nuclear material stays in peaceful use, the fuel is measured with two complementary non‐destructive methods to verify the integrity and the fissile content of the fuel prior to disposal. For pin‐wise identification of active fuel material, a Passive Gamma Emission Tomography (PGET) device is used. Gamma radiation emitted by the fuel is assayed from 360 angles around the assembly with highly collimated CdZnTe detectors, and a 2D cross‐sectional image is reconstructed from the data. At the encapsulation plant in Finland, there will be the possibility to measure in air. Since the performance of the method has only been studied in water, measurements with mock‐up fuel were conducted at the Atominstitut in Vienna, Austria. Four different arrangements of activated Co‐60 rods, steel rods and empty positions were investigated both in air and in water to confirm the functionality of the method. The measurement medium was not observed to affect the ability of the method to distinguish modified rod positions from filled rod positions. More extended conclusions about the method performance with real spent nuclear fuel cannot be drawn from the mock‐up studies, since the gamma energies, activities, material attenuations and assembly dimensions are different, but full‐scale measurements with spent nuclear fuel are planned for 2023

    Simultaneous emission and attenuation reconstruction in passive gamma emission tomography of spent nuclear fuel

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    In the context of international nuclear safeguards, the International Atomic Energy Agency (IAEA) has recently approved passive gamma emission tomography (PGET) as a method for inspecting spent nuclear fuel assemblies (SFAs). The PGET instrument is essentially a single photon emission computed tomography (SPECT) system that allows the reconstruction of axial cross-sections of the emission map of an SFA. The fuel material heavily self-attenuates its gamma-ray emissions, so that correctly accounting for the attenuation is a critical factor in producing accurate images. Due to the nature of the inspections, it is desirable to use as little a priori information as possible about the fuel, including the attenuation map, in the reconstruction process. Current reconstruction methods either do not correct for attenuation, assume a uniform attenuation throughout the fuel assembly, or assume an attenuation map based on an initial filtered back-projection reconstruction. We propose a method to simultaneously reconstruct the emission and attenuation maps by formulating the reconstruction as a constrained minimization problem with a least squares data fidelity term and regularization terms. Using simulated data, we show that our approach produces clear reconstructions which allow for a highly reliable classification of spent, missing, and fresh fuel rods

    Improved Passive Gamma Emission Tomography image quality in the central region of spent nuclear fuel

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    Reliable non-destructive methods for verifying spent nuclear fuel are essential to draw credible nuclear safeguards conclusions from spent fuel. In Finland, spent fuel items are verified prior to the soon starting disposal in a geological repository with Passive Gamma Emission Tomography (PGET), a uniquely accurate method capable of rod-level detection of missing active material. The PGET device consists of two highly collimated detector banks, collecting gamma emission data from a 360° rotation around a fuel assembly. 2D cross-sectional activity and attenuation images are simultaneously computed. We present methods for improving reconstructed image quality in the central parts of the fuel. The results are based on data collected from 2017 to 2021 at the Finnish nuclear power plants with 10 fuel assembly types of varying characteristics, for example burnups from 5.7 to 55 GWd/tU and cooling times from 1.9 to 37 years. Data is acquired in different gamma energy windows, capturing the peaks of Cs-137 (at 662 keV) and Eu-154 (at 1274 keV), abundant isotopes in long-cooled spent nuclear fuel. Data from these gamma energy windows at well-chosen angles are used for higher-quality images, resulting in more accurate detection of empty rod positions. The method is shown to detect partial diversion of nuclear material also in the axial direction, demonstrated with a novel measurement series scanning over the edge of partial-length rods
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