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26 articles for “Nuclear reactor safety”
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Mathematical Derivation and Stability Analysis of a Coupled Neutron Kinetics–Thermal Feedback Model for Nuclear Reactor Safety
Abstract: Nuclear reactor safety assessment requires accurate characterization of the coupled interaction between neutron population dynamics and thermal feedback during steady-state operation and transient conditions. This study develops a mathematically derived coupled neutron kinetics–thermal feedback model for analysing reactor stability and transient behaviour. The formulation integrates point reactor kinetics with delayed-neutron precursor dynamics, fuel-temperature evolution, coolant- temperature variation, and temperature-dependent reactivity feedback. The reactor is represented as a nonlinear dynamical system …
Published in Journal of Nuclear Engineering & Technology · Vol. 16, Issue 2, 2026 Read article
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Nuclear Reactor Safety Using Fuel Pallet: A Study
Abstract: Nuclear power stands as a vital source of low-carbon electricity, but its widespread acceptance hinges critically on unwavering safety. While public perception often focuses on massive containment buildings, intricate cooling systems, and redundant backup power, a less visible yet fundamentally crucial component plays a paramount role in safety. There is much more to these tiny, cylindrical ceramic pellets than just fissionable material. As an essential part of a reactor's defense-in-depth …
Published in Journal of Nuclear Engineering & Technology · Vol. 15, Issue 3, 2025 · pp. 16–23 Read article
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Reimagining Nuclear Reactor Safety: The Study toward Passive Safety
Abstract: Nuclear power has been at a crossroads for decades. Acclaimed for its massive, decarbonized energy production, it has also been questioned because of the disastrous possibility of mishaps. Nuclear power remains a vital component of the global energy mix, offering a low-carbon, high- capacity solution to growing energy demands. However, its widespread adoption has historically been tempered by public safety concerns, amplified by incidents like Chernobyl and Fukushima. Traditional reactor …
Published in Journal of Nuclear Engineering & Technology · Vol. 15, Issue 3, 2025 · pp. 6–15 Read article
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Nuclear Reactor Safety Using Seismic and Natural Disaster Protection: A Study
Abstract: Nuclear energy has enormous power and is essential to the global effort to provide clean, sustainable electricity, but it also carries a huge responsibility: guaranteeing its complete safety. Nuclear energy is at a turning point. Nuclear power provides a potent, carbon-free answer as the globe struggles with climate change and the pressing need to decarbonize energy grids. However, public fear, primarily from past mishaps like Chernobyl and Fukushima, continues to …
Published in Journal of Nuclear Engineering & Technology · Vol. 16, Issue 1, 2026 · pp. 25–34 Read article
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A Study on Innovations in Primary Containment Technology for Safer Nuclear Power
Abstract: Nuclear power is a powerful carbon-free energy source that balances enormous potential with widespread public fear. Fear of radioactive leakage, a catastrophic catastrophe that might have long-lasting effects on the environs and human health, is at the core of this anxiety. The future of nuclear energy depends on finding a solution to this issue, and at the heart of that debate is the idea of primary containment, a technological marvel …
Published in Journal of Nuclear Engineering & Technology · Vol. 15, Issue 3, 2025 · pp. 37–44 Read article
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A Survey of Genetic Algorithm Applications in Nuclear Fuel Management
Abstract: The prime aim of nuclear fuel management is to achieve higher fuel utilization without compromising safety during reactor operation. Nuclear fuel management optimization is a classical nuclear engineering problem, which has been studied for more than four decades and several techniques have been used for its solution. Genetic algorithm is one among the major global optimization techniques, used in the field of nuclear fuel management. Aim of this paper is …
Published in Journal of Nuclear Engineering & Technology · Vol. 4, Issue 1, 2014 · pp. 45–62 Read article
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Wireless Sensor Network in Fast Breeder Test Reactor
Abstract: The second stage of India’s three-stage nuclear energy programme envisages of the development of Sodium cooled fast breeder reactors. As a forerunner, Fast Breeder Test Reactor (FBTR) at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam has been constructed. It is being operated successfully for more than 27 years. FBTR provides experience in fast reactor operation, fuel behavior, large scale sodium handling and is serving as a test bed for …
Published in Journal of Nuclear Engineering & Technology · Vol. 3, Issue 1, 2013 · pp. 28–36 Read article
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Three level Dashpot oil level monitoring system
Abstract: Nuclear reactors use free fall of control and safety rods (CSR) for a fast shutdown of the reactor in case of emergencies to prevent radioactive hazards. During the last 250mm of the total 1085mm of travel of the CSRs, there is a dashpot with oil to facilitate the smooth descent of the control rods. This oil prevents any shock to the system due to the sudden fall. Thus, there is …
Published in Journal of Nuclear Engineering & Technology · Vol. 12, Issue 2, 2022 · pp. 48–55 Read article
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The Next Era of Nuclear Engineering: Beyond Fission
Abstract: Nuclear engineering is going through a big change as new technologies strain the limits of classical fission-based power generation. This article talks about the future generation of nuclear technologies, such as new reactor designs, small modular reactors (SMRs), and the growing potential of nuclear fusion. It looks at how these changes are meant to make nuclear energy safer, use less fuel, and create less long-lived radioactive waste, which are all …
Published in Journal of Nuclear Engineering & Technology · Vol. 16, Issue 1, 2026 · pp. 35–41 Read article
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Design Boiling Water Reactor Core Model Using MCNPX for Studying the Burnable Poisons and the Axial Enrichment Fuel Effect on the Neutronic Characteristics
Abstract: The incorporation of gadolinium directly into nuclear fuel is important for improving the reactor behavior and satisfying the safety criteria during the core lifetime. MCNPX (Monte Carlo N–Particle code extended) has been used for designing Advanced Boiling Water Reactor model. MCNPX code based on Monte Carlo method, is used to design a three-dimensional model for a BWR fuel assembly in a typical operating temperature and pressure conditions. This model has …
Published in Journal of Nuclear Engineering & Technology · Vol. 3, Issue 1, 2013 · pp. 21–35 Read article
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Nuclear Power as a Clean Energy Future: A Review
Abstract: The global push for decarbonization necessitates a diverse energy portfolio, and nuclear power, once a subject of intense debate, is re-emerging as a potential cornerstone of a clean energy future. With its capacity for baseload power generation and minimal greenhouse gas emissions during operation, nuclear energy offers a compelling substitute for fossil fuels, particularly in a world grappling with climate change. However, challenges remain regarding safety, waste disposal, and economic …
Published in Journal of Nuclear Engineering & Technology · Vol. 15, Issue 2, 2025 · pp. 1–11 Read article
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Performance Analysis of a Naval Reactor for Nuclear Powered Ship
Abstract: AbstractNuclear power-driven ships are becoming progressively more popular in advancing ship technology. Nuclear ships use naval reactors, which have lower fuel costs and last for many years and have almost zero emissions. The working of a Nuclear Ship is derived from the simple nuclear fission reaction. One more important factor that has spurred on the continuous investigates of nuclear power generation within ships is the irregular cost of flammable fuels. …
Published in Journal of Nuclear Engineering & Technology · Vol. 8, Issue 1, 2018 · pp. 1–6 Read article
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Ghana’s Nuclear Power Option and Associated Safeguards Technique
Abstract: The adequate supply of electricity is a pre-requisite for industrialization, sustainable development and a key policy agenda for national development. Economic consumption of electricity production would have to be augmented to satisfy Ghana’s high level of economic growth and social well-being in the future. In 2008, cabinet decision was taken to proceed with the nuclear power plant construction roadmap. As part of the preparations being made towards the implementation of …
Published in Journal of Nuclear Engineering & Technology · Vol. 6, Issue 2, 2016 · pp. 1–5 Read article
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Safety Management in Indian Nuclear Power Plants
Abstract: AbstractNuclear industry goes to great lengths to ensure that safety takes overriding priority in siting, design, construction, and operation of nuclear power plants. There are well established safety principles and practices, which are followed internationally. The principle of defence in depth is followed in toto, to ensure that safety provisions are adequate and consequences would be acceptable. Management of safety is carried out by the regulating authority through periodic safety …
Published in Journal of Nuclear Engineering & Technology · Vol. 10, Issue 2, 2020 · pp. 29–37 Read article
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Study of Stainless Steel’s Properties for Radiation Safety using Artificial Neural Networks
Abstract: Several general components of reactor are made from stainless steel. Most of the container used for storing nuclear waste is made from stainless steel. In this work, an artificial neural networks (ANNs) model is used to improve the properties of stainless steel during its manufacturing process. The main job of ANNs is determining the layer’s thickness and predicting the influence of different parameters on the growth kinetic of the process. …
Published in Journal of Nuclear Engineering & Technology · Vol. 8, Issue 3, 2018 · pp. 31–40 Read article
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Safety System Analysis of Nuclear Power Plant in Bangladesh
Abstract: In this paper, the safety system and safeguards of the model VVER-1000, which is a Gen-III pressurized water reactor, designed by ROASTAM and chosen to be implemented in Bangladesh, will be analyzed. Several predefined major faults have been set to demonstrate the performance in preventing the release of harmful radiation. From simulation results, it has been observed that for moderator dilution, the malfunction is neutralized within 115 sec, for turbine …
Published in Trends in Electrical Engineering · Vol. 6, Issue 3, 2016 · pp. 11–25 Read article
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Thorium Nuclear Reactor: A Sustainable Future for Clean Energy-A Review Study
Abstract: Thorium-232, a naturally abundant and fertile element, is increasingly regarded as a viable alternative to uranium-235 as the basis of future nuclear fuel cycles. This review examines the physical and nuclear properties that make thorium attractive as a reactor fuel, the mechanics of the thorium- uranium-233 fuel cycle, and the principal reactor concepts developed to exploit it, including pressurized heavy water reactors, pressurized water reactors, fast breeder reactors, advanced heavy …
Published in Journal of Nuclear Engineering & Technology · Vol. 16, Issue 2, 2026 Read article
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Parallel Genetic Algorithm for Fuel Bundle Burnup Optimization of Pressurized Heavy Water Reactor
Abstract: In this study, parallel genetic algorithm (GA) was applied to solve an optimization problem of nuclear fuel management pertaining to a 220 MWe pressurized heavy water reactor (PHWR). The study aims at finding appropriate values of reference discharge burnups of two zones of the reactor core which gives maximum fuel economy, while satisfying operational and safety-related constraints. This is a multiobjective optimization problem with four objectives and four constraints. Penalty …
Published in Journal of Nuclear Engineering & Technology · Vol. 6, Issue 1, 2016 · pp. 11–24 Read article
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Recurrent Neural Network Model for Signal Prediction in a LOCA Event
Abstract: Normal 0 false false false MicrosoftInternetExplorer4 In this study, an artificial neural network (ANN) model with the Elman recurrent structure is developed to predict thermo-hydraulic signals in a loss of coolant accident (LOCA). In the prediction procedure, a few previous samples of a signal at the time of the accident are fed to the ANN and the output value of next time steps are estimated by the network output. The …
Published in Journal of Nuclear Engineering & Technology · Vol. 1, Issue 2-3, 2011 · pp. 13–24 Read article
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Criticality Risk Assessment during Transportation and Storage of MTR Spent Fuel Elements
Abstract: Abstract This study aims to evaluate the criticality condition during transporting the spent fuel elements from the temporary storage to the permanent storage by using a Latin American cask. The cask was developed to transport the material testing reactor (MTR) fuel element type. MCNP5 code was used to calculate the criticality, expressed in terms of the neutron multiplication factor (k-effective), for normal and accidental situations using 21 fresh fuel elements. …
Published in Journal of Nuclear Engineering & Technology · Vol. 9, Issue 1, 2019 · pp. 1–6 Read article