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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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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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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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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Research on bubble generation method based on flow control mechanism
Available online 28 August 2023
The method of bubble generation is the key to the application of bubbles, of which the flow control method is widely used because of its low energy consumption and high efficiency, and the flow mechanism...
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Advanced nuclear power engine: A brief overview of gas core reactor for space exploration
June 2023
Space travel requires propulsion with high specific impulse. Gas core reactors using plasma nuclear fuel operate at high temperature (104-105K) and theoretically produce higher specific impulses (2500-7000s)...
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The modeling of passive containment cooling system and sensitivity analysis using the SPRUCE code
June 2023
Passive Containment Cooling Systems (PCCSs) have attracted wide attention to improve the inherent safety of nuclear power plants. This study summarizes a system analysis method of a closed-loop natural...
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Prediction of heat transfer coefficients for steam condensation in the presence of air based on ANN method
June 2023
Artificial neural network (ANN) methods have been gradually used in the field of nuclear reactor thermal-hydraulics as new methods to improve accuracy or fast prediction. This study establishes a back...
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Study on iterative algorithm of full plate cross-flow and counter-flow printed circuit heat exchanger for fluoride-salt-cooled high-temperature advanced reactor
June 2023
In the concept of Fluoride-Salt-cooled high-Temperature Advanced Reactor (FuSTAR), the Printed Circuit Heat Exchanger (PCHE) is mainly considered in its supercritical carbon dioxide (S–CO2) Brayton...
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Analysis of containment pressure control strategy in HPR1000 NPP under severe accidents
June 2023
Containment is the last barrier of preventing the release of radioactive fission products in a nuclear power plant (NPP). It has the top priority of its strategy in a severe accident (SA) to ensure...
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Phenomena identification Ranking Table (PIRT) study for suppression containment of small modular reactor using new methodology
June 2023
The Phenomena Identification and Ranking Table (PIRT) is a significant method for analyzing the safety of nuclear reactors. It helps researchers identify important phenomena within the reactor, enabling...
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The evaporation of nanoscale sodium liquid film on the non-ideal nanostructure surface: A molecular dynamics study
March 2023
The nanoscale liquid sodium film inside the microporous wick structure is of great importance to understanding the evaporation mechanism of the sodium heat pipe. The novel optimized wick structure is...
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A criticality assessment through user's routines in FLUKA
March 2023
In the present paper, a method to obtain the keff value using the FLUKA code is described. It took advantage of the chance to write user defined routines in the standard code. A new algorithm was implemented...
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Numerical investigation on transverse flow of helical cruciform fuel rod assembly in a lead-bismuth cooled fast reactor
March 2023
The helical cruciform fuel (HCF) rod assembly is a new type of fuel for the lead-bismuth (LBE) fast reactor. It can be self-positioned and realize a coolant mixing without wrapped wire or grid spacer....
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Influence analysis of alloy elements on irradiation embrittlement of RPV steel based on deep neural network
March 2023
Reactor pressure vessel (RPV) is the most important core equipment in PWR. Its service life determines the service life of nuclear power plant and directly affects the economy and safety of nuclear...
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Analysis of radiation shielding effectiveness of hydride and borohydride metals for nuclear industry
March 2023
Hydrogenous materials are of great interest in nuclear industry because of the ability of hydrogen to slow-down neutrons. In comparison with common hydrogenous materials, metal hydrides highly enriched...
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Development of an edge-cloud collaboration framework for fission battery management system
December 2022
As a “plug-and-play” nuclear system, the technology of fission battery enables nuclear reactor systems to function as batteries. Undoubtedly, advanced intelligent technologies have to be adopted to...
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Electrochemical behavior and corrosion rate prediction study of alloy 690
December 2022
Alloy 690 is a material commonly used in heat transfer tubes of steam generators (SGTs). The electrochemical corrosion behavior in different volumes (V) of NaCl–Na2S2O3 solution for different surface...
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Characteristic analysis of natural circulation residual heat removal in small reactor
December 2022
In order to study the characteristics of small helium-xenon cooled nuclear reactor that only relies on natural circulation to remove residual heat after shutdown, this paper carries out geometric and...
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Experimental investigation of nano-particle deposited wick Structure's heat transfer characteristics
December 2022
Recently, nanotechnology attracts more and more attention in heat transfer system. Many studies have shown that using nanofluid as the working fluid can improve the thermal performance of the heat pipe....
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Heat transfer performance of high temperature and high velocity hydrogen flow and analysis of blockage characteristics
December 2022
In the current situation of increasing demand for nuclear heat propulsion in various countries, the heat transfer characteristics of high temperature and high velocity fluid in the flow channel are...
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Melting and relocation behavior of metal and force balance analysis of metallic droplet
December 2022
In this paper, the heating, melting and relocation behavior of zinc was carried out based on the MEREA (Metal mElting and RElocation progression Apparatus) facility. Metal melt tests with different...
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Preliminary study on FROBA-SCO2 with transient models and its application for Reactivity Initiated Accident and loss of flow accident
September 2022
As a coolant enabling the reactor with a high efficiency and low volume, the supercritical CO2 has becoming a hot topic nowadays. However, the fuel rod behaviors under accidents are not studied thoroughly,...
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Development and evaluation of fuel performance analysis code FuSPAC
September 2022
The nuclear fuel rod should maintain self-sustainable nuclear fission, as the first safety barrier to prevent the leakage of radioactive products. The fuel rod performance analyses are essential to...
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Experimental Study of Turbulent Bubbly Flow in 180-Degree Elbow by PIV-PS Technique
September 2022
The curvature effect and bubbles are the key factors that affect the gas-liquid two-phase flow and turbulent characteristics in the 180-degree elbow. Limited by the difficulty of experimental measurement...
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