Results 21 to 30 of about 1,341 (152)

EVALUATION OF CRITICAL EXPERIMENTS IN THE UNIVERSITY OF WISCONSIN NUCLEAR REACTOR (UWNR) WITH UNCERTAINTY QUANTIFICATION [PDF]

open access: yesEPJ Web of Conferences, 2021
An improved computational model of the University of Wisconsin Nuclear Reactor (UWNR) was developed to support the benchmark evaluation of recent data acquired during an experimental campaign conducted at UWNR.
Park Young-Hui   +5 more
doaj   +1 more source

Validation of Monte Carlo simulations by experimental measurements of neutron-induced activation in cyclotrons [PDF]

open access: yesEPJ Web of Conferences, 2023
Nuclear activation is the process of production of radionuclides by irradiation. This phenomenon concerns particle accelerators used in various fields, from medical applications to industrial ones, both during operation and at the decommissioning phase ...
Collin Jonathan   +7 more
doaj   +1 more source

Study on kinetic parameters characteristics of pebble bed reactor using HTR-proteus facility [PDF]

open access: yesNuclear Technology and Radiation Protection, 2022
The inherent safety feature of a pebble-bed reactor can be observed from its kinetic parameters. Proper modeling for calculating the reactor kinetic is also a concern for safe operation during normal and transient conditions.
Zuhair   +4 more
doaj   +1 more source

NEUTRON DEPTH PROFILE CALCULATIONS USING ARTIFICIAL NEURAL NETWORKS [PDF]

open access: yesEPJ Web of Conferences, 2021
Neutron depth profiling (NDP) is a non-destructive technique used for identifying the concentration of impurity isotopes below the sample surface. NDP is carried out by detection of the emitted charged particles resulting from bombarding the sample with ...
Hossny K.   +4 more
doaj   +1 more source

Study on kinetic parameters of pebble bed reactor with TRISO duplex fuel [PDF]

open access: yesNuclear Technology and Radiation Protection, 2023
Thorium, in this case, 232Th has a higher thermal neutron capture cross-section than 238U, which means that more fertile isotopes can be transmuted and could lead to higher fissile isotope 233U.
Zuhair   +4 more
doaj   +1 more source

Neutron flux distribution in (Pb,Ta and W) target using accelerator of 18 MeV electron beam

open access: yesEurasian Journal of Physics and Functional Materials, 2021
The production of neutrons can be carried out with the bombardment of the nuclei of heavy atoms, with accelerated and energetic particles (generally electrons). The electron collides with the target nuclei, so, 20 to 30 neutrons are produced by a process
A. Didi   +3 more
doaj   +1 more source

Characterization of control rod worths and fuel rod power peaking factors in the university of Utah TRIGA Mark I reactor [PDF]

open access: yesNuclear Technology and Radiation Protection, 2016
Control rod reactivity (worths) for the three control rods and fuel rod power peaking factors in the University of Utah research reactor (100 kW TRIGA Mark I) are characterized using the AGENT code system and the results described in this paper.
Alroumi Fawaz   +3 more
doaj   +1 more source

Assessment of TMSR-500 Shutdown Capability

open access: yesAtom Indonesia, 2022
The molten salt reactor (MSR) is a generation IV reactor with liquid fuel having nearly zero excess reactivity. Due to the very low excess reactivity, it requires a small number of control rods worth to shut down the reactor.
A. Khakim   +3 more
doaj   +1 more source

The use of self-induced X-ray fluorescence in gamma-ray spectroscopy of uranium ore samples [PDF]

open access: yesEPJ Web of Conferences, 2020
Gamma logging for uranium exploration are currently based on total counting with Geiger Müller gas detectors or NaI (TI) scintillators. However, the total count rate interpretation in terms of uranium concentration may be impaired in case of roll fronts,
Marchais T.   +7 more
doaj   +1 more source

Effect of MOX fuel and the ENDF/B-VIII on the AP1000 neutronic parameters calculations by using MCNP6 [PDF]

open access: yesNuclear Technology and Radiation Protection, 2019
The present work studies the effect of introducing MOX fuel on Westinghouse AP1000 neutronic parameters. The neutronic calculations were performed by using the MCNP6 code with the ENDF/B-VII.1 library and the new release of the ENDF/B-VIII ...
Reda Sonia M.   +3 more
doaj   +1 more source

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