Investigation of sodium fire aerosol diffusiophoresis deposition in concrete gaps during the processes within nuclear power plants
Available online 18 December 2024
Sodium fire accidents are among the high-risk incidents that nuclear power plants with sodium-cooled fast reactors pay close attention to. Sodium fire reactions can generate a considerable amount of...
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Analysis of Flow Distribution and Bypass Flow for DHR-400 Low Temperature Heating Reactor
Available online 16 December 2024
Flow distribution at the core inlet and the fraction of bypass flow are important aspects of thermal hydraulic design for reactor. Three-dimensional fluid dynamics analysis was used to numerically simulate...
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Optimization study of lead-based reactor heat exchangers based on Dakota coupling CFD
June 2024
The lead-bismuth fast reactor is one of the fourth-generation reactor types.The microchannel heat exchangers are used as intermediate heat exchangers, which significantly influence the efficiency of...
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Research on reactor power prediction of nuclear power plant based on multivariate optimization GRU model
June 2024
In the operation of nuclear power plants, the accurate prediction of power change trends is crucial for ensuring safety and stability. In this work, a ML-GRU-RS method, based on model-agnostic meta-learning...
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Method of out-of-pile high-temperature tests of low-melting materials in conditions of modeling a severe nuclear reactor accident
June 2024
This article is devoted to the technique for conducting experiments to study the nature of the interaction of low-melting metals with corium in the conditions of simulating a severe nuclear reactor...
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Investigate of electrochemical properties of Nd(II) and Nd(III) in eutectic LiCl–KCl molten salt
June 2024
Pyroprocessing is one of the promising methods to reprocess the spent nuclear fuel. Neodymium (Nd) constitutes about one third of rare earth in fission products, however, the electrochemical properties...
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Analysis of explosion incidents in nuclear fuel reprocessing facilities and recommendations for their prevention
June 2024
Human society endeavors to harness nuclear energy for peaceful utilization, intertwining it with global strategies to address pressing issues such as energy demand, environmental preservation, and energy...
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Machine learning for forecasting factory concentrations of nitrogen oxides from univariate data exploiting trend attributes
June 2024
The development of post-processing technology for spent nuclear fuel is essential to ensuring the sustainable growth of nuclear energy. However, post-processing facilities release copious amounts of...
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Advancements in the research of high-temperature gas-cooled reactor fuel via additive manufacturing techniques
March 2024
Recent advances in high-temperature gas-cooled reactor fuel research have captured the global spotlight, as modern operating contexts demand innovative responses to unprecedented challenges. This article...
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Validation of transient SYSTEM analysis code GINKGO based on a SLB TEST
March 2024
Transient System analysis code is an important tool for reactor thermal hydraulic analysis. GINKGO is a transient system analysis in-house code developed by China General Nuclear Power Corporation (CGN)....
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Investigation on crack propagation of SiCf/SiC composite via PF-CZM method
March 2024
SiCf/SiC composite materials had become a research hotspot in the fields of aerospace materials and nuclear materials in recent years. This materials have high strength, radiation resistance, high temperature...
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Multi-objective optimization research of open and closed air brayton cycle
March 2024
Air Brayton cycle obtains the significant advantages of high efficiency, compact structure, easy medium requirement and so on, which is one of the most suitable choices for the mobile nuclear power...
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Experimental study on thermal-hydraulic performance of helically coiled tubes steam generator of lead-bismuth reactor
March 2024
The advantages of the helically coiled tube steam generator lie not only in its high heat transfer efficiency but also in its compact structure, which is initially used in Pb–Bi–SCO2 reactors, and its...
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The main structural-phase states of interaction between model corium of a nuclear reactor and a sacrificial material based on Al2O3 and a lead layer
March 2024
This article presents the results of post-experimental studies of the interaction of model light water reactor corium with a candidate sacrificial material (SM) based on Al2O3 (corundum) and a lead...
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Investigation on numerical simulation models for heat transfer characteristics of lead-bismuth eutectic
March 2024
The liquid lead-bismuth eutectic (LBE) has distinct thermal and physical properties that challenge the effectiveness of traditional RANS turbulence models and turbulent Prandtl number (Prt) models for...
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Research on thermal stratification of surge line in the marine reactor based on fluid-solid thermal coupling model
December 2023
Due to the requirements of ship movement, the power of the marine reactor is constantly changing, and the expansion and contraction of the primary coolant make the fluid flow in and out through the...
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Research on characteristic of flow instability in a two-phase natural circulation loop with parallel once-through steam generators
December 2023
When there are two sets of parallel once through-steam generators(OTSG) in the natural circulation loop, the thermal-hydraulic characteristics are complicated. Flow instability often occurs in such...
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Conceptual design of a novel megawatt portable nuclear power system by supercritical carbon dioxide brayton cycle coupled with heat pipe cooled reactor
December 2023
In order to meet realistic requirements for flexible and reliable power supply in special scenarios such as remote areas and deep ocean exploration, a novel megawatt portable nuclear power system called...
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Uncertainty analysis of molten corium In-Vessel Retention under External Reactor Vessel Cooling
December 2023
External Reactor Vessel Cooling (ERVC) is a key measure to realize molten corium In-Vessel Retention (IVR). The uncertainty of severe accident in core leads to the uncertainty of molten pool parameters...
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Research of aerosol removal by passive containment cooling system
December 2023
Passive containment cooling system (PCCS) can effectively remove the heat from the containment and maintain the pressure and temperature in case of accident, thus ensuring the containment integrity....
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Experimental study of the interaction between molten corium and new sacrificial material for ex-vessel melt retention
December 2023
Ex-vessel melt Retention (EVR) is one of the important countermeasures to address the issue of basement melt penetration in the course of a hypothetical severe accident in a nuclear power plant. Specifically...
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Numerical simulation and structural optimization of spiral finned tube thermal energy storage
September 2023
Thermal energy storage (TES) has emerged as a promising solution to enhance nuclear safety by passively removing decay heat during reactor shutdown and accidents, thus preventing overheating of the...
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Advanced manufacturing technologies for enhancing security in nuclear and radiological materials transport
September 2023
Advanced manufacturing technologies have transformed various industries, including nuclear security areas such as nuclear and radiological transport. This review manuscript describes the intersection...
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Excitation function of neutron induced reaction on isotopes of cadmium (106Cd, 108Cd &110Cd) in the energy range of 13–15 MeV
September 2023
This study focuses on the theoretical calculations of neutron-induced reaction cross-sections on several stable isotopes of cadmium within the energy range of 13–15 MeV. The nuclei produced in this...
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Analysis of thermal hydraulic system code LOCUST V1.2 with ECC thermal mixing test facility
September 2023
The safety injection (SI) system might be put into use, and the coolant at high temperature will mix with the supcooled water under Loss Of Coolant Accident (LOCA). The thermo-hydraulic phenomena associated...
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