Oxidation kinetics of Cr-coated zirconium alloy: Effect of coating thickness and microstructure

EB Kashkarov, DV Sidelev, MS Syrtanov, C Tang… - Corrosion …, 2020 - Elsevier
Cr coatings with the thickness of 4.5–9.0 μm and dense/columnar microstructure were
deposited onto Zr alloy by cooled or hot target magnetron sputtering. Steam oxidation tests …

Nanofluid application for heat transfer, safety, and natural circulation enhancement in the NuScale nuclear reactor as a small modular reactor using computational …

Z Rahnama, GR Ansarifar - Progress in Nuclear Energy, 2021 - Elsevier
In recent years,“Nanofluid” and “Energy-Efficient Cooling” have been achieved growing
attention for use in new nuclear reactor technology. Also, the assurance of reactor safety has …

Nickel-chromium (Ni–Cr) coatings deposited by magnetron sputtering for accident tolerant nuclear fuel claddings

DV Sidelev, EB Kashkarov, MS Syrtanov… - Surface and Coatings …, 2019 - Elsevier
Nickel-chromium coatings were deposited on Zrsingle bond1Nb alloy using magnetron
sputtering systems with «hot» Ni and cooled Cr targets. The effect of coating composition on …

Annular fuel for VVER-1000 reactor: Moderation impact on neutronic behavior

MT Ahmed, A Shelley - Progress in Nuclear Energy, 2023 - Elsevier
The impacts of moderation on the neutronic behavior of the VVER-1000 reactor assembly
have been investigated by using annular fuel and compared with the conventional one. The …

Predicting and optimizing the thermal-hydraulic, natural circulation, and neutronics parameters in the NuScale nuclear reactor using nanofluid as a coolant via …

Z Rahnama, GR Ansarifar - Annals of Nuclear Energy, 2021 - Elsevier
This investigation studies the optimization of water-based alumina nanofluid to advance
heat transfer and safety performance of the NuScale natural circulation reactor. First …

Design of the CAREM nuclear reactor core with dual cooled annular fuel and optimizing the thermal-hydraulic, natural circulation, and neutronics parameters

S Nasiri, GR Ansarifar, MH Esteki - Annals of Nuclear Energy, 2022 - Elsevier
The small modular nuclear reactor (SMR) with annular fuel which is cooled internally and
externally has the potential to maintain high power density with a sufficient safety margin …

Thermal-Hydraulic modelling and analysis of VVER-1200 reactor core

SED El-Morshedy, MM Awad, MA El-Fetouh - Annals of Nuclear Energy, 2023 - Elsevier
A mathematical model has been developed to simulate the thermal–hydraulic performance
of the VVER-1200 pressurized water reactor under normal operation. The energy equation …

Numerical investigations on the melting process of the nuclear fuel rod in RIAs and LOCAs

J Tang, M Huang, Y Zhao, S Maqsood… - International Journal of …, 2018 - Elsevier
In light water reactor, melting of nuclear fuel rod (NFR) is critical. Therefore, this issue needs
to be simulated and analyzed with different accidental conditions. In this paper, one …

Optimal design of a Small Modular Reactor core with dual cooled annular fuel based on the neutronics and natural circulation parameters

MZ Nejad, GR Ansarifar - Nuclear Engineering and Design, 2020 - Elsevier
Abstract Small Modular Reactors (SMRs) are the creative design of nuclear reactors that
have received considerable attention in recent years. Since there is insufficient operational …

Optimal design of a VVER-1000 nuclear reactor core with dual cooled annular fuel based on the reactivity temperature coefficients using thermal hydraulic and …

R Kianpour, GR Ansarifar, M Fathi - Annals of Nuclear Energy, 2020 - Elsevier
One of the approaches which can help the enhancement of a reactor power is changing its
fuel geometry. For this purpose, as well as decreasing the maximum fuel temperature in …