Abstract: In cooperate with Nuclear Power Institute of China, Changjiang Institute of Survey, Planning, Design and Research has completed the demonstration concept design research of underground nuclear power plant and proposed the underground nuclear power plant with independent intellectual property rights ...
Abstract: On the basis of the independent research and development achievements, in cooperation with Changjiang Institute of Survey, Planning, Design and Research, Nuclear Power Institute of China（NPIC） finished the conceptual design of Chinese underground nuclear power plant, and proposed the design scheme f...
Abstract: Experiments prove that the relations between the natural circulation capacity G and the heating power Q, and the total flow resistance Δpf and the natural circulation capacity G are: G~Qm and Δpf~Gq, respectively. Power indexes of m and q are defined as the natural circulation flow rate-heating powe...
Abstract: In order to analyze the liquid fueled molten salt reactor using RELAP5 code, models in RELAP5 code need to be extended. This paper attempts to add new point kinetic model of liquid fueled reactor and thermo-hydraulics model with internal heat source based on the original RELAP5 models, then the code...
Abstract: Based on liquid sublayer dryout mechanism, a critical heat flux（CHF） model has been developed for the prediction of DNB-type CHF. In the model, the forces exerted on the vapor blanket are analyzed to calculate the boiling crisis parameters including vapor blanket velocity, sublayer thickness with mo...
Abstract: Micro-scale bubble growth, coalescence and heat transfer characteristics are numerically investigated. Bubble interface is tracked with VOF（Volume of Fluid） method in CFD（Computational Fluid Dynamics） software. A 3 mm×2 mm×2 mm 3-D micro-channel is set up and 5 heating elements are arranged at the b...
Abstract: The natural circulation lead-bismuth cooled reactor is an important direction for the reactor development. Understanding of the natural circulation flow characteristics of lead-bismuth is crucial to the development of natural circulation lead-bismuth cooled reactor. Experimental modeling similarity ...
Abstract: Based on the first law of thermodynamics, a thermodynamic investigation was carried out on the coupling supercritical carbon dioxide Brayton cycles. The thermodynamic behavior and parameter limitations of the recompression cycle have been analyzed for a heat source system on the basis of equipment m...
Abstract: In order to analyze the structures of packed beds, the discrete element method（DEM） reveals great advantages for numerical simulation. There are only few particles at densest state in random packed beds. Porosity increases rapidly with the oscillation at near-wall region. More local microstructure i...
Abstract: Based on the statistics of 350 sets of strong-motion acceleration records on bedrock in Next Generation Attenuation（NGA） database of the US and 14 sets of strong-motion acceleration records on bedrock in Wenchuan MW7.9 earthquake and Lushan MW6.6 earthquake, normalized horizontal spectral accelerati...
Abstract: Dynamic artificial boundary is a necessary means to using the 3D finite element technique to solve the dynamic problem of foundation. Based on the viscoelastic boundary and the transmitting boundary developed, the seismic response analysis of a building structure in a typical example of nuclear powe...
Abstract: In the seismic risk analysis for the nuclear power plant, the appropriate data processing method and analytical technique are required. In this study, seismic risk quantification software is developed independently for the first time in China. It uses Monte Carlo sampling method to simulate the seis...
Abstract: ZrCo alloys with Ti substitution were prepared via the arc-melting method, and then the products before and after hydrogenation were characterized by X-ray diffraction. Results showed that the crystal structure of ZrCo alloys substituted with Ti substitution formed cubic phase, and the lattice param...
Abstract: The effect of temperature on pickling rate of zirconium alloy and the heat release constant was studied in this paper by soaked method. The results show that temperature has exponential effect on pickling rate of zirconium alloy, the rate increases 2.0~2.5 times 10℃ at 20~60℃. The pickling frequency...
Abstract: Under the stimulated nuclear plant water environment, corrosion property and oxide film characteristics of three kinds of commercial 690 alloys for steam generators were studied in the flow-water corrosion loop. Meanwhile, the general corrosion rate and corrosion product release rate were also estim...
Abstract: Simulating the water chemistry of the PWR primary loop, the impact wear tests of stellite-6 which used in CRDM were carried out at different temperature and different impact force by using a specially designed impact wear test device. Results showed that the effect of temperature was not obvious whe...
Abstract: Steam generator tube rupture（SGTR） accident is a significant design basis accident which shall be analyzed in PWR nuclear power plant safety analysis reports. Thermo-hydraulic analysis of SGTR accident for licensing has been done using a specific code entitled LOFTTR2. To validate the applicability ...
Abstract: In this paper, we introduce many kinds of uncertainty quantification methods used in realistic LBLOCA analysis, and quantify the uncertainties of the output of large break loss of coolant accident based on the best estimate thermal hydraulic system code CATHARE GB LBLOCA model of CPR1000 nuclear pow...
Abstract: In the containment hydrogen analysis, there is uncertainty in the computation results because uncertainty exists in the input parameters. It is of great importance for the safety issue to study the variation ranges of the computation results as well as the contribution of each input parameter to the...
Abstract: In order to study the effect of blade inlet position on flow characteristics of nuclear reactor coolant pump under gas-1iquid two-phase condition, three different schemes of inlet position had been designed and simulated on steady and unsteady stage under gas-liquid two-phase condition. The analysis...
Abstract: To achieve the experimental scheme study of the AP containment, H2TS method was used to carry out the system-level scaling and the result showed the prominent distortion of area-volume ratio. Based on the basic criteria of volume-power ratio, the Bottom-Up scaling approach was used to analyze the in...
Abstract: With the demand for life extension and the design life improvement for the in-service and new nuclear power plants, the neutron flux becomes higher during the irradiation of structural materials used in the nuclear reactors, leading to a sharp increase in material irradiation time. Correspondingly, ...
Abstract: Aiming at the risk of internal and external leakage for the damper in the nuclear power plants, some design measures for solving the internal and external leakage have been proposed. By the leakage tests before and after the seismic test, the seal design rationality of the damper is demonstrated. Ba...
Abstract: The printed circuit heat exchanger is a kind of compact heat exchanger, which geometry design method is studied based on the flow and heat transfer correlation. After the analysis of the design input, an analysis program was developed with the help of a mathematical software Matlab in this paper. Co...
Abstract: Firstly the Nuclear safety laws and guidelines was introduced briefly, and then the requirement of safety systems in nuclear safety laws and guidelines was decrebied, and the adaptability of passive core cooling system and passive containment cooling system commissioning to laws and guidelines was a...
Abstract: To find a better way to control the leakage characteristics of the reactor containment static sealing structure, the present work proposed a new leakage rate prediction model. In this model, the micro-mechanism of the static sealing is described based on the porous media seepage theory, and Hertz co...
Abstract: The cladding tube is the main component of the nuclear fuel assembly, and as the first protective barrier, its quality is very important for the safe operation of nuclear power plants. After the completion of cladding tubes, a non-destructive testing is required, in which the ultrasonic inspection i...
Abstract: During the generation of the thin bed on the containment sump Strainer, the particular debris and the fiber debris with the small size will pass though the strainer and go into the Safety Injection System（RIS）/ Containment Spray System（EAS） flow path. The debris effect on the downstream equipment sh...
Abstract: During the power test（COC53） for the 125 V DC power supply system（LBA） of Unit 3 of Ling’ao PhaseⅡNuclear Power Station, due to the loss of electricity, the circulating water pump（3CRF001PO） sewage pump pit cannot start the automatic drainage. The power failed for more than 6 h, and the water entere...
Abstract: Under the approach of numeral simulation, this paper firstly aims to carry out the simulating calculation work of value under different operating conditions and value lift, and then analyzes the erosion damage of the internal components of the value, which include value core, cage and seat. From thi...
Abstract: A method is designed to predict the configuration of the corium pool in the lower plenum of reactor vessel. It takes into account both thermo-chemical reaction of corium and the influence of different paths of corium relocated from core region into the lower plenum. The prediction by this method is ...
Abstract: In this paper, based on the investigation results of domestic and foreign countries for core damage assessment methods, we proposed a suitable core damage assessment method for current nuclear power plants of operation and under-construction in China, namely CDAG and IAEA TECDOC-955 approach, and a ...
Abstract: Advanced Stirling convertor designed by Sunpower was investigated as the object of the study, and a theoretical model of a Stirling cycle was established. Based on the operation condition of the nuclear power plant in the space, the theory of finite time thermodynamics was adopted to investigate the...
Abstract: A mathematical model was established to simulate the combustion of the premixed hydrogen and oxygen in this paper,and the influences of the ignition position,the reaction mechanism and elementary reaction kinetic parameters on the combustion process were analyzed. The results show that buoyancy has ...
Abstract: An experimental investigation is carried out to study the FCI process as the high superheated molten metals contact with the subcooled water during the severe accident of nuclear reactors. In this study, the characteristics of FCI processes with different molten metals and initial temperatures are a...
Abstract: A simplified model is developed to simulate the AP1000 containment pressurization under design basis accidents（DBAs）. The containment response has been performed by WGOTHIC code for comparison purpose. It shows a good agreement between the model and WGOTHIC code prediction results on containment hea...
Abstract: The numerical simulation for the design of the hot gas mixing structure of Pebble-bed Module High Temperature gas-cooled Reactor（HTR-PM） are carried out with consideration of the leakage flow out of the reactor core. According to the profiles of temperature, pressure drop and flow velocity, the ther...
Abstract: General perturbation theory（GPT） is applied to study the contribution of the nuclear data to the uncertainty of the macroscopic cross section（XS） of fuel assembly of AP1000. Through the comparison and analysis of the contribution of the different uncertainty sources, the correlation matrix of macros...
Abstract: The market prospect of the combined heat and power generation in China was analyzed, and the feasibility of high temperature reactor for combined heat and power generation（HTR-CHP） was studied in technical and economic aspects. The results show that HTR-CHP can balance the operation safety and heati...
Abstract: In nuclear industry some components will be radioactive from neutron induced activity. Radiation safety should be taken into consideration when the sample is measured. Considering the neutron diffraction technique and radiation safety, a method for measuring the radioactive sample is proposed and a ...
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Sponsored by: Nuclear Power Institute of China
Editorial Office: Nuclear Power Branch of China Nuclear Society
