A peer-reviewed journal published by K. N. Toosi University of Technology
Benchmark MCNP computer code simulation results against experimental data of neutron flux and spectrum from neutron imaging system of Tehran research reactor

Majid Zamani; Mohsen Shayesteh

Volume 5, Issue 1 , January 2024, , Pages 11-19

https://doi.org/10.22034/rpe.2023.406935.1152

Abstract
  Using the experimental data in nuclear computing to verify the calculation methods and tools based on numerical and statistical methods has many benefits such as illustrating the quality, ensuring the capabilities, and computer codes validating. Simulation by computer tools is also applicable in the ...  Read More

Modeling the partial loss of coolant flow accident in the Super-critical water reactor

Mohammad Hossein Bahrevar; Gholamreza Jahanfarnia; Ali Pazirandeh; Mohsen Shayesteh

Volume 2, Issue 3 , September 2021, , Pages 31-39

https://doi.org/10.22034/rpe.2021.306279.1042

Abstract
  In this study, thermal-hydraulic analysis of partial loss of coolant flow accident in supercritical pressure light water reactor (SCWR) with a new geometric design has been investigated. In the new design, the coolant and moderator circuits are separated. This analysis was performed using the development ...  Read More

Neutronic analysis of different patterns of ABV reactor core using low enrichment UO2 fuel

Javad Karimi; Mohsen Shayesteh; Mehdi Zangian

Volume 2, Issue 2 , June 2021, , Pages 37-42

https://doi.org/10.22034/rpe.2021.286704.1030

Abstract
  Today, small modular reactors have received considerable attention in various countries. The ABV reactor is a PWR small modular reactor that has various applications. This reactor has been used silumin metal fuel with a 16.5% enrichment. In the present work, the efficiency of the conventional UO2 fuel ...  Read More

Investigation of molten material retention during the large and small breaks LOCA and station blackout accident

Mohsen Salehi; Mohsen Shayesteh

Volume 1, Issue 4 , October 2020, , Pages 17-27

https://doi.org/10.22034/rpe.2020.104840

Abstract
  ‎The analysis deals with the assessment of best estimate code RELAP5/SCDAP mod3.4 in the simulation of double-ended loss coolant accident as a LBOCA‎, ‎4 in break as a SBLOCA an SBO accident with considering except accumulator water where no core cooling water systems are available‎. ...  Read More