A peer-reviewed journal published by K. N. Toosi University of Technology
Radiation hazards from granite and bitumen in construction material site in Aniocha South Local Government Area of Delta State, South-South Nigeria

Blessing Okeoghene Ijabor; Akintayo Daniel Omojola; Augustine Onyema Nwabuoku; Funmilayo Ruth Omojola

Volume 4, Issue 2 , March 2023, Pages 1-8

https://doi.org/10.22034/rpe.2022.342868.1090

Abstract
  The study is aimed at measuring the outdoor background ionizing radiation (BIR), the absorbed dose rate (ADR), the annual effective dose (AED) and excessive lifetime cancer risk (ELCR) at four sites in the Aniocha South local government area (LGA) of Delta State, denoted as A-D. The study was performed ...  Read More

Studying the effect of backgrounds on the determination of radiative thermal neutron capture cross-section in the Neutron Powder Diffraction facility of the Tehran Research Reactor

Mahya Pazoki; Hamid Jafari; Zohreh Gholamzadeh

Volume 4, Issue 2 , March 2023, Pages 9-17

https://doi.org/10.22034/rpe.2022.349750.1094

Abstract
  Neutron data and cross-sections are highly regarded and are essential for developing nuclear equipment such as advanced fission and fusion reactors, accelerators, neutron shielding, physics studies, etc. The neutron cross-section should preferably be measured using a single-energy neutron beam, although ...  Read More

Effect of marker material on the dosimetric parameters of I-125 source (model 6711): Monte Carlo simulation

Payvand Taherparvar; Ali AziziGanjgah

Volume 4, Issue 2 , March 2023, Pages 19-24

https://doi.org/10.22034/rpe.2022.338851.1079

Abstract
  Low energy I-125- seeds are considered as a common source in different brachytherapy techniques for treatment of different cancers. In this study, at first, we simulated and validated I-125 (model 6711) seed according to the TG-43U1 recommendation, by GEANT4 Monte Carlo toolkit. Moreover, we simulated ...  Read More

Computational study of the effect of sapphire neutron filter on reducing the neutron and secondary-gamma dose rate around the main shield of D channel in TRR

Zohreh Gholamzadeh

Volume 4, Issue 2 , March 2023, Pages 25-33

https://doi.org/10.22034/rpe.2022.353820.1099

Abstract
  Simulation work provides valuable information on the behavior of different research reactor neutron analysis facilities. The present study considered neutron and secondary-gamma dose rate variations by applying a sapphire crystal inside the D channel in Tehran Research Reactor (TRR). The MCNPX computational ...  Read More

Design and construction of the plasma water activation device

Malihe Omrani; Hossein Sadeghi; Samaneh Fazelpour

Volume 4, Issue 2 , March 2023, Pages 35-37

https://doi.org/10.22034/rpe.2022.336236.1068

Abstract
  Design, construction, and experimental investigation of the plasma water activation device have been presented in this article. In this design, one of the electrodes, which is plate ss316, is placed in water. The other electrode which is made from tungsten is placed inside a glass tube and immersed in ...  Read More

Investigation of Radiation-Matter Interaction Effects on Burn Process of Nonequilibrium Deuterium-Tritium Plasma in Inertial Confinement Fusion Approach

Mehdi Nazirzadeh; Babak Khanbabaei; Hamidreza Alborznia

Volume 4, Issue 2 , March 2023, Pages 39-44

https://doi.org/10.22034/rpe.2022.339578.1083

Abstract
  A numerical model was developed and a system of the nonlinear equations of deuterium-tritium burn-up in inertial confinement fusion have been solved to find the minimum conditions which are required for the formation of hot spot and starting the thermonuclear reactions in a self-sustaining mode. The ...  Read More

Calculation of the role of Wigner energy in decontamination of Cs-137 from irradiated Graphite pores ‎

Mohammad Nikoosefat; Ardeshir Bagheri; Hamid Reza Shakur; Zahra Shahbazi Rad; Nabi Javadi

Volume 4, Issue 2 , March 2023, Pages 45-51

https://doi.org/10.22034/rpe.2022.340253.1084

Abstract
  During the operation of Graphite -fuel HTGR (High-Temperature Gas-cooled Reactor) nuclear reactors, Graphite  used as a neutron moderator, is irradiated and has a variety of contaminants (such as Cs-137, Co-60, and Sr-90) and due to industrial and environmental considerations, decontamination of ...  Read More

Assignment of a radiological map of the city of Borujerd in Iran

Reza Pourimani; Mobin Bajelan; Monire Mohebian

Volume 4, Issue 2 , March 2023, Pages 53-60

https://doi.org/10.22034/rpe.2022.370078.1108

Abstract
  The specific activity of radionuclides in the soil of the Borujerd region using high purity Germanium detector (HPGe) was measured and the associated radiological hazards were calculated. The mean specific activity of radionuclides of Ra-226, Th-232, K-40, and Cs-137 in soil was obtained at 10.99±5.11, ...  Read More