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Volume & Issue: Volume 1, Issue 4, Winter 2023 
Number of Articles: 6

Design, Simulation and Evaluation of Pressure Control System in a High-pressure Research Test loop

Pages 1-9

https://doi.org/10.48308/nucte.2023.101467

Seyed Ali Hosseini

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  • PDF 543.44 K

Fire simulation in the control room of Bushehr nuclear power plant by CFAST software

Pages 10-14

https://doi.org/10.48308/nucte.2023.101468

Sahar Mojab, Ehsan Zarifi, Gholam Reza Jahanfarnia, Masoud Mansouri

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  • PDF 461.61 K

Investigation of Increasing Safety and Reliability of Small Modular Reactors Using Dual-cooled Annular Fuel Element

Pages 15-22

https://doi.org/10.48308/nucte.2023.101469

majid zaidabadi nejad

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  • PDF 764.74 K

Evaluation of the Safety Systems of Tehran Research Reactor Fuel Test Loop during Loss of Flow Accident

Pages 23-31

https://doi.org/10.48308/nucte.2023.101470

saiedeh safaei arshi

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  • PDF 655.39 K

Thermo-Hydraulic Analysis of Passive Heat Removal System (PHRS) in VVER-1000 Nuclear Reactor Using RELAP5 Code

Pages 32-42

https://doi.org/10.48308/nucte.2023.101471

Saeed Zare Ganjaroodi

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  • PDF 1.15 M

Conceptual Design and reactivity control of long-life and LEU soluble boron free Hexagonal Fuel Assembly

Pages 43-52

https://doi.org/10.48308/nucte.2023.103498

Majid Hosseinllu

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  • PDF 820.56 K
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