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Advances in High-Temperature Irradiation-Resistant Neutron Detectors. [PDF]
Wang C, Yu R, Xia W, Gong J.
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Calculation of the gamma and neutron dose field inside JSI TRIGA Mark II reactor hall
V tej disertaciji je opisano, kako lahko stohastične metode uporabimo za računanje doznega polja v okolici reaktorja TRIGA. Simuliramo lahko tako normalno obratovanje reaktorja kot tudi nezgodne dogodke. Poznavanje doz je ključno za zagotavljanje varnega delovnega mesta operaterjem in raziskovalcem.
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Optimization of a pre-concentration method for the analysis of mercury isotopes in low-concentration foliar samples. [PDF]
Ali SW +8 more
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Impact of the Guard Rings on Self-Induced Signal and Leakage Current in Trench-Isolated Low Gain Avalanche Diodes. [PDF]
Lastovicka-Medin G +3 more
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Postbiotics derived from recombinant lactic acid bacteria exhibit high IL6-binding capacity and suppress IL6-induced STAT3 signaling. [PDF]
Zahirović A +6 more
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In 2016, the NATO Science for Peace and Security Programme funded research project "Engineering SiliconCarbide for Border and Port Security" — E-SiCure was launched, its objective being the development ofradiation-hard silicon carbide (SiC) based detectors of special nuclear materials (SNM), with the aim to enhanceborder and port security barriers ...
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Computational analysis of the dose rates at JSI TRIGA reactor irradiation facilities
Applied Radiation and Isotopes, 2017The JSI TRIGA Mark II, IJS research reactor is equipped with numerous irradiation positions, where samples can be irradiated by neutrons and γ-rays. Irradiation position selection is based on its properties, such as physical size and accessibility, as well as neutron and γ-ray spectra, flux and dose intensities.
Gasper Žerovnik +2 more
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Computational analysis of irradiation facilities at the JSI TRIGA reactor
Applied Radiation and Isotopes, 2012Characterization and optimization of irradiation facilities in a research reactor is important for optimal performance. Nowadays this is commonly done with advanced Monte Carlo neutron transport computer codes such as MCNP. However, the computational model in such calculations should be verified and validated with experiments.
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