Showing papers in "Annals of Nuclear Energy in 2022"

TL;DR: A literature survey of 160 published articles (1981-2021) showed that DGR is the most ideal solution for long-term storage of the PUNF, as it provides an ultimate destination in a deep underground that permanently isolates the waste from inhabitants and the environment as mentioned in this paper.

TL;DR: A literature survey of 160 published articles (1981-2021) showed that DGR is the most ideal solution for long-term storage of the PUNF, as it provides an ultimate destination in a deep underground that permanently isolates the waste from inhabitants and the environment as mentioned in this paper .

TL;DR: In this paper, the authors presented the sensitivity analysis of thermal and hydraulic parameters in the repository by using COMSOL multiphysics, and proposed a new buffer barrier with double layers consisting of buffer-A with higher heat conductivity closing to the HLW canister and buffer-B with lower hydraulic conductivity closed to surrounding rock.

TL;DR: In this article , the authors presented the sensitivity analysis of thermal and hydraulic parameters in the repository by using COMSOL multiphysics, and proposed a new buffer barrier with double layers consisting of buffer-A with higher heat conductivity closing to the HLW canister and buffer-B with lower hydraulic conductivity closed to surrounding rock.

TL;DR: In this article , the authors consider a nuclear hybrid energy system that uses a mixture of salt and coal for power generation and demonstrate the potential of using salt as either a coolant for solid fuel or a fuel salt.

TL;DR: In this article , the authors used machine learning algorithms to predict the acceptance of the reopening of the Bataan Nuclear Power Plant (BNPP) by utilizing decision tree, Random Forest Classifier (RFC), and Artificial Neural Network (ANN) as a highlight to predict human behavior.

TL;DR: In this article , a physics-based approach for system-level diagnosis in thermal-hydraulic systems in nuclear power plants is described, which allows for the creation of virtual sensors, which provide improved fault diagnosis capability.

TL;DR: In this article , the OpenMC/OpenFOAM code system is developed for a neutronic analysis of very high temperature gas cooled reactor (VHTR) and two different scale problems including PWR assembly and core benchmark are used to assess the accuracy of DiFOAM V1.0.

TL;DR: In this paper , the authors proposed an ensemble learning approach to mitigate the negative impacts of the problems of nuclear power plants by combining multiple machine learning models into a composite model, where the basic idea of ensemble learning is that even if one model makes a mistake, other models can correct it.

TL;DR: In this paper , a novel approach based on physics-informed neural networks (PINNs) for the solution of Point Kinetics Equations (PKEs) with temperature feedback is presented.

TL;DR: In this article , a data-based fault diagnosis method was proposed to improve the accuracy and speed of fault diagnosis in small pressurized water reactors (SPWRs) by combining principal component analysis (PCA) and support vector machine theory.

TL;DR: The results show that the robustness of the models varies greatly under different data taint modes, and the AND method can significantly improve the anti-noise robustity of RF model.

TL;DR: Wang et al. as mentioned in this paper proposed a convolutional network (CNN)-based transfer learning method to solve the problem of rotating machines fault diagnosis, which requires only limited training data to achieve high accuracy.

TL;DR: In this article, a new speedup algorithm that can consider the flow and heat-transfer simulations separately is proposed to handle the multi-time-scale problem in debris remelting and the influence of debris size and decay heat power on the occurrence of local hot spots and RPV breach patterns during debris melting was investigated.

TL;DR: In this article , the authors proposed an approach that combines reduced-order models with machine learning in order to create an operational digital twin to predict the power distribution over the core during the operation stage.

TL;DR: In this paper , a new speedup algorithm that can consider the flow and heat-transfer simulations separately is proposed to handle the multi-time-scale problem in debris remelting, and the influence of debris size and decay heat power on the occurrence of local hot spots and RPV breach patterns during debris melting was investigated.

TL;DR: This study shows that core power is controlled by CTO based IMC-PI controller, which is optimized with Class topper optimization (CTO) algorithm which improves robustness of the control scheme.

TL;DR: In this article , a novel model training method named "Add Noisy Data" (AND) is proposed to improve the anti-noise ability of the models by adding noisy data to the training set.

TL;DR: In this paper , a series feedback combination of fuzzy and PID controllers is designed to resolve the reactor power control problem for VVER-1000 PWR, where a nonlinear multipoint kinetic model based on neutron diffusion, thermal hydraulics, spatial neutronics and poison effect is developed for dynamic simulation with three groups of delayed neutrons.

TL;DR: In this paper, a nearly autonomous management and control system (NAMAC) is proposed to assist plant operations by furnishing control recommendations to operators in a broad class of situations.

TL;DR: In this article , the authors applied Unsteady Reynolds-Averaged Navier-Stokes (URANS) to predict axial friction factor under the presence of blockages.

TL;DR: In this paper , the authors developed a high-temperature heat pipe transient analysis code that takes into account the non-condensable gas (NCG) effect, which can make the start-up process go more smoothly.

TL;DR: In this article , a 65.5 MWth heat pipe cooled traveling wave (HPTWR) design is proposed, which uses neutron traveling wave to improve the continuous operation time and reduce the enrichment of loaded fuel comparing to the currently existing heat pipe reactor designs.

TL;DR: In this paper , a nearly autonomous management and control system (NAMAC) is proposed to assist plant operations by furnishing control recommendations to operators in a broad class of situations.

TL;DR: In this article, a series feedback combination of fuzzy and PID controllers is designed to resolve the reactor power control problem for VVER-1000 PWR, where a nonlinear multipoint kinetic model based on neutron diffusion, thermal hydraulics, spatial neutronics and poison effect developed for dynamic simulation with three groups of delayed neutrons.

TL;DR: A fuzzy fault accommodation (FFA) method for nuclear power plants under actuator stuck faults can adjust the plant target load dynamically to match the reactor power during transients in which a few of the actuators lose their regulating capacity completely.

TL;DR: In this paper, the authors applied Unsteady Reynolds-Averaged Navier-Stokes (URANS) to predict axial friction factor under the presence of blockages.

TL;DR: In this article , the authors proposed a fuzzy fault accommodation (FFA) method for nuclear power plants under actuator stuck faults, which can adjust the plant target load dynamically to match the reactor power during transients in which a few of the actuators lose their regulating capacity completely.

TL;DR: In this paper , the impact of multiphysics simulations for predicting the core characteristics of the Versatile Test Reactor, which is being designed as a 300MWt sodium-cooled fast reactor, was evaluated.

TL;DR: In this paper, a set of models are established for the lithium-cooled space reactor combined with the Stirling engine, and the result of the steady-state is checked with the maximum relative error of 13.3%.