Results 61 to 70 of about 5,021 (94)

Calculation of the gamma and neutron dose field inside JSI TRIGA Mark II reactor hall

open access: yes, 2020
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.
openaire   +1 more source

Optimization of a pre-concentration method for the analysis of mercury isotopes in low-concentration foliar samples. [PDF]

open access: yesAnal Bioanal Chem
Ali SW   +8 more
europepmc   +1 more source

Silicon carbide neutron detector testing at the JSI TRIGA reactor for enhanced border and port security

open access: yesSilicon carbide neutron detector testing at the JSI TRIGA reactor for enhanced border and port security
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 ...
openaire  

Evaluation of neutron flux and fission rate distributions inside the JSI TRIGA Mark II reactor using multiple in-core fission chambers

open access: yes, 2018
Tanja Kaiba   +6 more
semanticscholar   +1 more source
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Computational analysis of the dose rates at JSI TRIGA reactor irradiation facilities

Applied Radiation and Isotopes, 2017
The 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
exaly   +4 more sources

Computational analysis of irradiation facilities at the JSI TRIGA reactor

Applied Radiation and Isotopes, 2012
Characterization 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.
Gasper Žerovnik   +2 more
exaly   +3 more sources

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