Thaar Mohammad Aljuwaya

Dr. Thaar Mohammad Aljuwaya

Nuclear Technologies Institute (NTI), King Abdulaziz City for Science and Technology, Riyadh, Ar Riyāḑ, Saudi Arabia
orcid

Research Focus & Metrics

Academic Career Length

8Years (2019-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

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21 September 2023 in Sustainability
Verified
Journal Article
Open access
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FFFarah G. Fahad
Farah G. Fahad
SAShurooq talib Al-Humairi
Shurooq talib Al-Humairi
AEAmged Al Ezzi
Amged Al Ezzi
HMHasan Majdi
Hasan Majdi
Abbas J. SultanAbbas J. Sultan
Abbas J. Sultan
TAThaar Mohammad Aljuwaya
Thaar Mohammad Aljuwaya
Desiccant agents (DAs) have drawn much interest from researchers and businesses because they offer a potential method for lowering environmental impact, increasing energy efficiency, and controlling humidity. As a result, they provide a greener option to conventional air conditioning systems. This review thoroughly analyzes current issues, obstacles, and future advancements in liquid desiccant agents (LDAs) for drying, air conditioning, and dehumidification applications. The importance of LDAs in lowering energy use and greenhouse gas emissions is highlighted, emphasizing their potential for environmentally friendly humidity control. The current review examines key parameters such as novel materials, enhancing desiccant qualities, integration with technologies, and long-term durability while examining recent developments in LDAs and investigating their applications in diverse industries. The main conclusions from the evaluated publications in this review are also highlighted, including developments in LDAs, new applications, and developing research fields. Overall, this review advances knowledge of LDAs and their potential to shift humidity control systems toward sustainability and energy efficiency.

1 August 2019 in Chemical Engineering Research and Design
Verified
Journal Article
Closed access
TAThaar Mohammad Aljuwaya
Thaar Mohammad Aljuwaya
NANeven Ali
Neven Ali
Muthanna Al-DahhanMuthanna Al-Dahhan
Muthanna Al-Dahhan

5 February 2022 in Sensors
Verified
Journal Article
Open access
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AAAhmed Alghamdi
Ahmed Alghamdi
TAThaar Mohammad Aljuwaya
Thaar Mohammad Aljuwaya
AAAbdullah S. Alomari
Abdullah S. Alomari
Muthanna Al-DahhanMuthanna Al-Dahhan
Muthanna Al-Dahhan
In the past two decades, the radioactive particle tracking (RPT) measurement technique has been proven to visualize flow fields of most multiphase flow systems of industrial interest. The accuracy of RPT, and hence the data obtained, depend largely on the calibration process, which stands here as a basis for two subsequent processes: tracking and reconstruction. However, limitations in the RPT calibration process can be found in different experimental constrains and in assumptions made in the classical Monte Carlo approach used to simulate number of counts received by the detectors. Therefore, in this work, we applied a GEANT4-based Monte Carlo code to simulate the RPT calibration process for an investigated multiphase flow system (i.e., gas–liquid bubble column). The GEANT4 code was performed to simulate the number of counts received by 28 scintillation detectors for 931 known tracer positions while capturing all the types of photon interaction and overcoming solids’ angle limitations in classical approaches. The results of the simulation were validated against experimental data obtained using an automated RPT calibration device. The results showed a good agreement between the simulated and experimental counts, where the maximum absolute average relative deviation detected was about 5%. The GEANT4 model typically predicted the number of counts received by all the detectors; however, it over-estimated the counts when the number of primary events applied in the model was not the optimal.

14 August 2023 in Nuclear Engineering and Technology
Verified
Journal Article
Open access
MVMehul S. Vesvikar
Mehul S. Vesvikar
TAThaar Mohammad Aljuwaya
Thaar Mohammad Aljuwaya
MTMahmoud M. Taha
Mahmoud M. Taha
MAMuthanna H. Al-Dahhan
Muthanna H. Al-Dahhan

5 January 2023 in Processes
Verified
Journal Article
Open access
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FZFaraj M. Zaid
Faraj M. Zaid
Haider Al-RubayeHaider Al-Rubaye
Haider Al-Rubaye
TAThaar Mohammad Aljuwaya
Thaar Mohammad Aljuwaya
Muthanna Al-DahhanMuthanna Al-Dahhan
Muthanna Al-Dahhan
The most common scale-up approach for gas–solids fluidized beds is based on matching the governing dimensionless parameters. In the literature, this approach has been validated only by means of measuring global parameters between different sizes of fluidized beds. However, such global measurements are not sufficient to depict all the interplaying hydrodynamic phenomena and hence verify the scale-up relationships. Therefore, to assess this approach, an advanced gas–solids optical probe and pressure transducer measurement techniques have been applied to quantify local hydrodynamic parameters in two different sized fluidized beds. Four different sets of experimental conditions were designed and conducted to examine the assessment of the scaling approach with matched and mismatched dimensionless groups between the two beds. The results indicated that the reported dimensionless groups are not adequate for achieving similarity between the two gas–solids fluidized beds in terms of solids holdup, gas holdup, particle velocity, mass flux, and pressure fluctuation. This finding demonstrates the importance of local measurements of the hydrodynamic parameters of fluidized beds in order to evaluate scale-up relationships. Finally, the results further advance the understanding of the gas–solids fluidized beds and present deeper insight into their solids dynamics.

30 March 2023 in Processes
Verified
Journal Article
Open access
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TAThaqal M. Alhuzaymi
Thaqal M. Alhuzaymi
MAMeshari ALQahtani
Meshari ALQahtani
TAThaar Mohammad Aljuwaya
Thaar Mohammad Aljuwaya
AAAyodeji B. Alajo
Ayodeji B. Alajo
Utilization of nuclear research reactors is of high importance for education and training, research and development, and many other applications. However, less effective utilization encountered in research reactors is mainly due to limitations in power levels and related experimental facilities. Such limitations, however, have led different global owners of research reactors to consider upgrading the power levels of their reactors to accommodate the increase in utilization demands. To consider upgrading the power levels of research reactors without replacing major components, a pair of essential analyses must be performed, namely the neutronic evaluation of nuclear fission and thermal-hydraulic evaluation for heat removal from the reactor core. In this work, a conceptual upgrade to the core design and configuration of MSTR, or Missouri University of Science and Technology Reactor (200 kilowatts (kW)), is demonstrated. The conceptual design of the MSTR high-power configuration (MSTR-HPC) aims to achieve high neutron flux and demonstrate the power level and core configuration with greater flexibility and adaptability while not exceeding safety limits. The conceptual design of the MSTR-HPC involves uprating the power level to 2 megawatts (MW), reconfiguring the core, changing the fuel meat type, inclusion of a flux trap (FT) facility, and others. In addition, the conceptual design of MSTR-HPC includes three in-core irradiation facilities, namely FT, bare rabbit tube (BRT), and cadmium rabbit tube (CRT). The neutronic evaluation of the MSTR-HPC was carried out using the Monte Carlo N-particle Code (MCNP), version 6. In addition, the thermal-hydraulic behavior of MSTR-HPCs’ hot-channel has been assessed by means of ANSYS Fluent to evaluate the satisfaction of thermal-hydraulic safety requirements of the conceptual design. The results obtained have shown that the conceptual MSTR-HPC has demonstrated a maximum neutron flux obtained higher than that obtained in the current MSTR core by two orders of magnitude. The conceptual design of MSTR-HPC with composite BeO/graphite reflector blocks was able to sustain critically and operate continuously at full power for 61 days. In regards to the hottest fuel plate of MSTR-HPC, the results have shown that the determined temperature for the fuel plate regions was below the safety limits. In addition, at full operation power of the MSTR-HPC, the mass flow rate of 39.86 kg/s (10.644 gallon/s) was sufficient for removing the generated heat. In conclusion, the conceptual design of the MSTR-HPC has demonstrated its flux enhancement capabilities while maintaining safety limits, which are of high importance in enhancing reactor utilization for a larger window of time.