Electrochemical sensor for uranium monitoring in natural water based on poly Nile blue modified glassy carbon electrode
Z Zhou, Y Zhou, X Liang, J Luo, S Liu, J Ma - Journal of Solid State …, 2022 - Springer
Herein, a novel strategy for sensitive determination of uranium in natural water was
proposed using electropolymerization of Nile blue modified glassy carbon electrode …
proposed using electropolymerization of Nile blue modified glassy carbon electrode …
Design and fabrication of a sensitive electrochemical sensor for uranyl ion monitoring in natural waters based on poly (brilliant cresyl blue)
Z Zhou, Y Zhou, X Liang, J Luo, S Liu, J Ma - Microchimica Acta, 2022 - Springer
New insights are proposed into enhancing detection of uranyl ions (UO22+) by
electropolymerization brilliant cresyl blue–modified glassy carbon electrode (PBCB/GCE) …
electropolymerization brilliant cresyl blue–modified glassy carbon electrode (PBCB/GCE) …
Rapid quantitative elemental analysis using artificial neural network for case study of Isfahan Miniature Neutron Source Reactor
A Asgari, SA Hosseini - Journal of Radioanalytical and Nuclear Chemistry, 2022 - Springer
In this study, new method for NAA purposes at 30 kW Isfahan MNSR is suggested. An
algorithm based on ANN is proposed to quantitatively predict the unknown elements with no …
algorithm based on ANN is proposed to quantitatively predict the unknown elements with no …
Sensitive detection of uranium in water samples using differential pulse adsorptive stripping voltammetry on glassy carbon electrode
Z Zhou, Y Zhou, X Liang, F Xie, S Liu, J Ma - Journal of Radioanalytical …, 2019 - Springer
Direct and rapid determination of trace amounts of uranium in natural water remains a
challenge. Herein, determination of uranium by differential pulse adsorptive stripping …
challenge. Herein, determination of uranium by differential pulse adsorptive stripping …
Conceptualization of the Micro Research Reactor Cooled by Heat Pipes (MRR-HP), Part-I: neutronics analyses
This work aims to introduce a new neutrons source technology for research and medical
applications, by the conceptualization of the M icro R esearch R eactor cooled by H eat P …
applications, by the conceptualization of the M icro R esearch R eactor cooled by H eat P …
The feasibility of 198Au production in Isfahan MNSR research reactor through a multi-stage approach
F Seyfi, B Soleimani, MA Hosseini… - … of Radioanalytical and …, 2018 - Springer
This study explored the feasibility to produce 198 Au in the Isfahan miniature neutron source
reactor (MNSR). To estimate production level, we used the MCNP simulation method …
reactor (MNSR). To estimate production level, we used the MCNP simulation method …
Monte Carlo simulation and practical investigation of body organs activation by Am–Be neutron source
A Nouraddini-Shahabadi, MR Rezaie… - Journal of the Korean …, 2024 - Springer
Employees and cancer patients are exposed to neutron radiation from different sources for
treatment. Neutrons when passing from body can activate organs. In this research first, it is …
treatment. Neutrons when passing from body can activate organs. In this research first, it is …
Feasibility of 153Sm production using MNSR research reactor through a multi-stage approach
B Soleimani, MA Hosseini, M Rezvanifard… - Applied Radiation and …, 2018 - Elsevier
The main objective of this study was to explore the feasibility of producing 153 Sm
radioisotope in miniature neutron source reactors (MNSRs) in Isfahan-Iran. As the first step …
radioisotope in miniature neutron source reactors (MNSRs) in Isfahan-Iran. As the first step …
[HTML][HTML] Development of a 3D thermohydraulic-neutronic coupling model for accident analysis in research miniature neutron source reactor (MNSR)
To accurately analyze the accidents in nuclear reactors, a thermohydraulic-neutronic
coupling calculation is required to solve fluid dynamics and nuclear reactor kinetics …
coupling calculation is required to solve fluid dynamics and nuclear reactor kinetics …
[HTML][HTML] Neutronic assessment of BDBA scenario at the end of Isfahan MNSR core life
The present study aims to assess the excess induced reactivity in a Miniature Neutron
Source Reactor (MNSR) for a Beyond Design Basis Accident (BDBA) scenario. The BDBA …
Source Reactor (MNSR) for a Beyond Design Basis Accident (BDBA) scenario. The BDBA …