Abstract: The heat absorption of circulating working medium can be improved by using the mutual transformation of thermal energy and surface energy in the process of adsorption and separation of fluid molecules on the solid surface of nano-porous materials. In this paper, molecular simulation (molecular dynam...
Abstract: In order to study the solidification mechanism of lead-bismuth alloy in the reaction between lead-bismuth alloy and water caused by steam generator tube rupture (SGTR), in this paper, by coupling the VOF model, the Realizable k-ε turbulence model, the solidification heat transfer model, and using th...
Abstract: The shielding database generation module Shield_calc is developed in the nuclear data processing program NECP-Atlas. This module firstly uses NECP-Atlas to generate a database of fine-group neutron and photon cross sections in MATXS format which is irrelevant to the problem; then uses the ultrafine ...
Abstract: Ultra-high temperature lithium (Li) heat pipe cooled nuclear reactor has broad application prospects in the areas of deep-sea nuclear power and deep-space exploration due to its silence, small size and other advantages. In order to master the heat transfer characteristics of ultra-high temperature l...
Abstract: The most remarkable technical feature of HPR1000 PWR nuclear power plant is that the reactor adopts a core composed of 177 fuel assemblies (hereinafter referred to as “177 core”), which has complete independent intellectual property right. In order to deeply analyze its characteristics, this paper i...
Abstract: Based on the fundamental of nitrogen pressure stabilizing, the lumped parameter method is adopted to develop the nitrogen pressure stabilizing system transient simulation model, which breaks through the limitations of the existing independent stabilizer model, realizes the direct coupling between th...
Abstract: Taking the horizontal spiral tube steam generator (HST-SG) of European lead-cooled system (ELSY) as the research object, combined with its structural and operating parameters, this paper selects an appropriate heat transfer resistance model and develops a one-dimensional steady-state thermal hydraul...
Abstract: Studying the evolution characteristics of the instantaneous flow field downstream of the spacer grid in the rod bundle channel under flow fluctuation is of great significance to reveal the flow and heat transfer mechanism in the fuel assembly under ocean conditions. In this paper, the structure of t...
Abstract: Core flow zoning is an important means to achieve core outlet temperature flattening. Reasonable zoning can improve the reactor safety and economy. In this paper, the artificial intelligence optimization algorithm is coupled with the single channel model, and the calculation model of reactor core fl...
Abstract: Under the loss-of-coolant accident (LOCA), the two-phase countercurrent in downcomer is extremely likely to cause the vapor-liquid counter-current flow limitation (CCFL), which is not conducive to the smooth entry of emergency coolant into the core, which greatly affects the safety performance of th...
Abstract: In order to deeply study the key factors affecting the driving force of the primary loop system of the natural circulation lead-based fast reactor, taking the natural circulation lead-based fast reactor SNCLFR-10 as the research object, a steady-state operation model describing the natural circulati...
Abstract: In order to study the safety characteristics of 2000 kW high temperature and high pressure test loop in high flux engineering test reactor (HFETR) in the process of loss of power accident of main pump, the simulation model of test loop is established based on RELAP5 code, and the transient character...
Abstract: The design of core flow distribution is the key content of core structure optimization of natural circulation reactor, which is highly valuable for improving core economy and safety. In this paper, the local optimal flow distribution calculation model is constructed based on the reactor closed paral...
Abstract: In order to improve the accuracy and timeliness of flow pattern identification under the condition of small samples, an optimized identification model integrating wavelet packet decomposition (WPD), principal component analysis (PCA), genetic algorithm (GA) and support vector machine (SVM) is propos...
Abstract: In order to study the effect of tube bundle arrangement of heat exchanger in passive containment cooling system (PCCS) on the condensation heat transfer characteristics of steam containing air under natural convection conditions, the condensation heat transfer process in channels of single tube, sin...
Abstract: Considering the irradiation test index and fuel test safety, the operation requirements of high flux engineering test reactor (HFETR), the pressure difference fluctuation in the test section and other factors, in this paper, based on HFETR, the design and analysis of the fast reactor fuel slug irrad...
Abstract: In order to solve the problems of poor convergence and insufficient research on thermal shock performance in the simulation of thermal shock behavior of SiC composite cladding, this paper simulates the internal stress state of double-layer SiC composite cladding under Loss of Coolant Accident (LOCA)...
Abstract: The corrosion behavior of Zr-Sn-Nb in the simulated PWR primary circuit zinc-injected aqueous chemical environment was investigated by autoclave corrosion test to analyze the surrosion and oxide film morphology of Zr-Sn-Nb alloy in zinc-free and zinc-added aqueous chemical environment. The results s...
Abstract: Since the existing high-temperature gas-cooled reactor failed fuel separator roller adopts a straight-toothed rack, and the redirecting teeth are embedded on the rack, the fuel balls will collide when passing through the redirecting teeth, which is easy to cause the fuel balls to be damaged, and cau...
Abstract: To obtain the residual stress distribution of the large ring-type dissimilar metal weld in the reactor pressure vessel(RPV), and guide the structural design and manufacturing process optimization of the reactor pressure vessel, the dissimilar metal welding structure simulators of nickel base alloy a...
Abstract: The fuel assembly is prone to bend after long-term irradiation in the core, which affects the safe drop of the control rod. Therefore, it is urgent to study the influence mechanism of the control rod drop behavior under the deformation channel. By means of numerical simulation, the law of rod drop b...
Abstract: Small lead-based reactor has a wide range of applications and complex and changeable operating conditions. It is difficult to achieve good control of core power by using traditional control methods. In order to solve the problem that the parameters of the traditional linear quadratic Gaussian contro...
Abstract: In order to monitor the reactor core during the first cycle charging, shutdown and start-up of nuclear power plants, domestic and foreign nuclear power plants generally introduce two primary neutron source components in the core, but the primary neutron sources are imported from the United States, w...
Abstract: Stretch-out operation (SO) is an important means of flexible operation for PWR nuclear power unit. It is of great significance to study how to improve the safety and economy of the unit under SO mode. For the case of fluctuation of important parameters such as primary loop average temperature, core ...
Abstract: Taking the sealing structure of safety valve in nuclear reactor system as the research object, a three-dimensional rough surface model of sealing structure based on porous medium theory is established in this paper. The calculation formula of leakage rate of sealing structure is deduced by Darcy's l...
Abstract: The lead-bismuth main pump is the key conveying equipment of the primary circuit in a lead- bismuth cooled fast reactor, and its safe operation is essential to the safety of the lead- bismuth cooled fast reactor. The flow characteristics of liquid lead-bismuth alloy in the pump have an important imp...
Abstract: Supercritical carbon dioxide (sCO2) Brayton cycle is one of the main solutions of the Generation IV nuclear reactor energy conversion system. During the actual operation, sCO2 in the compressor may condense. As a result, the efficiency is reduced and the operation stability is affected. In this pape...
Abstract: In order to test the effect of repeated start-stop on the reliability and drag torque of the thrust bearing of the primary circuit main pump in sodium cooled fast reactor (SFR), a reliability statistical scheme was designed by using the dispersion coefficient method suitable for small samples, three...
Abstract: Due to the harsh service environment of nuclear-level electric valves, degradation and failure are easy to occur. Therefore, in order to accurately predict the performance degradation trend of nuclear-level electric valves, this study adopts a method based on Hilbert-Huang transform (HHT) and BP neu...
Abstract: Post-72h procedures are special procedures for passive nuclear power plants. In order to evaluate the necessity and sufficiency of post-72 h procedures for passive nuclear power plants, and optimize and improve their weak links, this study analyzes the overall logic of the design basis and operating...
Abstract: In order to effectively reduce the corrosion rate of reactor coolant system (RCP) materials of pressurized water reactor (PWR) units and effectively remove activated corrosion products, so as to reduce the exposure dose of workers to ensure the smooth progress of unit overhaul, a 3rd Generation PWR ...
Abstract: Aiming at the problem of how to select effective health indicators and reasonably construct the prediction model in the remaining useful life (RUL) prediction of roller screw pair of reactor control rod drive mechanism (CRDM), a new RUL prediction model of roller screw pair is proposed. The negative...
Abstract: The visual display of ultrasonic signal position of complex geometric welds in nuclear power plants has important reference value for defect judgment. The inner surface of the nozzle of reactor pressure vessel (RPV) in nuclear power plant usually has a certain inclination angle. By using the traditi...
Abstract: Fuel assembly loading and unloading is an important operation of nuclear power plant reactor refueling maintenance. Because of its special operating environment, the loading and unloading positioning accuracy of floating nuclear power plant is higher. Based on the tolerance modeling method of small ...
Abstract: The corrosion behavior of the welding simulators of three stainless steel cladding materials S32205, S32101 and S30403 in spent fuel pool of nuclear power plant was studied by soaking them for 6 months under the conditions of H3BO3 concentration of 2500 mg/L, SO42− concentration of 1500 mg/L, Cl− co...
Abstract: The structural response characteristics of typical research reactor fuel assembly collision process are numerically simulated. The stress response characteristics of the fuel assembly, the bearing characteristics of the positioning structure of the fuel element and the protective effect of the filli...
Abstract: In order to analyze the dynamic process of intermittent release of fission gas caused by UO2 fuel grain boundary bubble connection, so as to solve the problem that the radial release share predicted by the current diffusion model is inconsistent with the experimental measurement, a two-dimensional p...
Abstract: The current emergency management of research reactors in China dose not have different requirements for emergency preparedness and response of different types of research reactors. A graded approach is a good means of properly applying these requirements in light of the potential hazards associated ...
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Sponsored by: Nuclear Power Institute of China
Editorial Office: Nuclear Power Branch of China Nuclear Society
