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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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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Experimental study on flow characteristics of rectangular narrow channel
2020
Plate fuel elements is gradually used in advanced reactor structure design because of its advantages of high fuel consumption and high safety. The flow channel of the plate fuel element is a typical...
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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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Steady-state thermal fluids analysis for the HTR-PM equilibrium core
2021
The high temperature gas-cooled reactor-pebble bed module (HTR-PM), designed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, is a demonstration project of nuclear...
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Simulation study on thermal characteristics of primary coolant system of lead-bismuth cooled reactor
September 2022
According to the structural characteristics of the lead-bismuth (LBE) cooled reactor and the flow and heat transfer characteristics of the coolant, a real-time simulation model of the primary coolant...
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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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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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Assessment of radiological safety and emergency response of VVER-1200 type reactor
June 2022
We studied the radiological safety and emergency response of the VVER-1200 type nuclear power plant using the RASCAL 4.3 and HOTSPOT 3.1.2 codes for INES levels 5, 6, and 7 reactor accidents due to...
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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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Calculation of neutron flux and neutron visualization in a spherical reactor core applying a conceptual approach and drawing a comparison with the results obtained by the CITATION code
2021
In this research, a conceptual approach is presented to obtain the neutron flux at a reactor core. A simple spherical reactor core was analyzed by a mathematical model defined by Delphi programming...
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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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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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Heat-transfer characteristics of screw tube in one-side high heat load condition for fusion reactor divertor application
2021
In this study, the heat transfer characteristics of one-side heated screw tubes were analyzed using subcooled flow boiling experiments. The experiments were performed until the critical heat flux was...
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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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Calculation of flow heat transfer characteristics of liquid gallium
2021
In order to design a more compact small nuclear reactor, liquid metal gallium can be selected as the reactor coolant. Gallium is rarely used in reactor as liquid metal coolant, however, due to its excellent...
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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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Statistical research on 2/3 of the first core nuclear fuel cost in nuclear power plants
June 2022
In this present article, a systematical research and analysis is newly introduced on traditional investment estimation of nuclear power plants, where 2/3 of the first core nuclear fuel cost is incorporated...
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Study on startup characteristics of prototype once-through steam generator for China fast reactor
March 2022
Once-through steam generator (OTSG) is a vital heat transfer equipment of China Fast Reactor-600 (CFR-600), and its startup characteristics are of great importance to the safe operation of nuclear power...
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Optimization of the TRISO fuel particle distribution based on octahedral and icosahedral-based segmentation methods in the pebble-bed nuclear core
2020
The random distribution of TRISO fuel particles in the fuel elements may form local hotspots, thereby increasing the thermal stress on TRISO particle layers that may cause particle failures. Optimization...
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Improvement and evaluation of ATWS Protective Signal and mitigation system for ACPR1000 nuclear power plant
March 2022
At the event of Loss of Normal Feed Water-An Anticipated Transient without Scram (LOFW-ATWS) in ACPR1000 unit, there exists the primary overpressure risk probability when the regulation function of...
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Thermal-hydraulic performance evaluation of annular fuel based on modified FROBA-ANNULAR
2021
In this study, based on the modification of the pellet cladding mechanical interaction, gap closure process, and the cladding water corrosion model, Fuel Rod Behavior Analysis-ANNULAR (FROBA-ANNULAR)...
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Study on the thermal and geometrical parameters of helical coil once-through steam generator system
2021
Due to the special structure, helical coil once-through steam generators (HCOTSGs) can withstand greater thermal expansion stress, have a larger heat exchange area, and cause the secondary flow phenomenon...
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Investigation of kaolin - Granite composite bricks for gamma radiation shielding
2021
Gamma radiation shielding properties of baked and unbaked kaolin bricks produced with 0%,10%, 20%, 30%, 40%, 50% of granite have been experimentally and theoretically investigated. A 3 × 3 inches NaI(Ti)...
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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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