Small modular reactor full scope core optimization using Cuckoo Optimization Algorithm
R Akbari, DR Ochbelagh, A Gharib, JR Maiorino… - Progress in Nuclear …, 2020 - Elsevier
Abstract Small Modular Reactors (SMRs) with their excellent safety and economic features
will be in high demand in the near future. Most SMR designs have longer burn-up cycle …
will be in high demand in the near future. Most SMR designs have longer burn-up cycle …
Assessment of an integral small modular reactor during rod ejection accident by using DRAGON/PARCS codes
R Akbari-Jeyhouni, DR Ochbelagh, A Gharib - Progress in Nuclear Energy, 2018 - Elsevier
Small modular reactors (SMRs) have benefits like lower initial costs and investment risks,
higher safety features, longer refueling cycle and also beside than electricity production …
higher safety features, longer refueling cycle and also beside than electricity production …
Quantifying the impact of risk mitigation measures using SPAR-H and RCM Approaches: Case study based on VVER-1000 systems
S Kordalivand, R Akbari, M Abbasi - Nuclear Engineering and Design, 2024 - Elsevier
Abstract Probabilistic Safety Assessment (PSA) provides a systematic and quantitative
approach to assess the risk associated with different components and systems within a …
approach to assess the risk associated with different components and systems within a …
An innovative conceptual design and theoretical assessment of online production of short-lived radionuclides in nuclear reactors
This paper introduces a novel conceptual design and theoretical assessment of short-lived
radionuclide production using an online reactor-based approach. The proposed design …
radionuclide production using an online reactor-based approach. The proposed design …
Neutronic analysis of the LVR-15 research reactor using the PARCS code
A Dambrosio, M Ruščák, G Mazzini, A Musa - Annals of Nuclear Energy, 2018 - Elsevier
Research reactors, together with the computational codes, represent a valuable tool
combination to investigate over phenomena which can take place in nuclear power plants …
combination to investigate over phenomena which can take place in nuclear power plants …
Thermo-neutronic integrated coupling effects on nuclear reactor core calculations
R Akbari, J Mokhtari, Y Abbassi, SM Mirvakili… - Progress in Nuclear …, 2024 - Elsevier
Abstract Small Modular Reactors (SMRs) have gained significant attention as the next
generation of nuclear reactors due to their unique features, such as improved economic …
generation of nuclear reactors due to their unique features, such as improved economic …
[HTML][HTML] Implementation of dynamic start-up test experimental data as a main part of the nuclear code validation procedure: Developed RELAP5 model for VVER-1000
N Vahman, R Akbari - Nuclear Engineering and Technology, 2024 - Elsevier
The main purposes of start-up tests in nuclear power plants (NPPs) are to ensure safe and
reliable operation, verify system functionality, comply with regulatory requirements, optimize …
reliable operation, verify system functionality, comply with regulatory requirements, optimize …
Control rod ejection accident simulation and sensitivity analysis of large advanced pressurized water reactor
LAN Bing, PAN Xinyi, YU Shihe, YI Yan - Nuclear Techniques, 2023 - hjs.sinap.ac.cn
BackgroundCompared with the traditional pressurized water reactor (PWR), the core design
of large advanced PWR CAP1400 has significant changes, such as the increase in the …
of large advanced PWR CAP1400 has significant changes, such as the increase in the …
[HTML][HTML] A model for calculating the irradiation swelling of AgInCd absorber in nuclear control rods
H Chen, H Xiao, C Long, X Leng - Nuclear Engineering and Technology, 2024 - Elsevier
The actual swelling of AgInCd absorber might exceed the predicted swelling value after
years of service in pressurized water reactors, and the chemical and microstructural …
years of service in pressurized water reactors, and the chemical and microstructural …
PARCS code multi-group neutron diffusion constants generation using Monte Carlo method
A Pirouzmand, F Mohammadhasani - Progress in Nuclear Energy, 2016 - Elsevier
PARCS code is a three-dimensional (3D) reactor core simulator which solves the steady-
state and time-dependent multi-group neutron diffusion equations if the multi-group diffusion …
state and time-dependent multi-group neutron diffusion equations if the multi-group diffusion …