Abstract: The transient temperature and the transient mixing characteristics of RPV downcomer in AP1000 under four kinds of operation condition（CMT Hot Functional Test, CMT Injection and ADS, CMT Recirc with ACC / IRWST Injection and Normal RHR Operation） has been investigated using the computational fluid dy...
Abstract: The sub-critical module-fuel component is the core component of the sub-critical blanket in fusion–fission hybrid energy system. The thermal safety experiment for module-fuel component is the foundation and necessary step of obtaining thermal design principle, developing structure design and safety ...
Abstract: Experimental investigation of natural convection in a long vertical annulus closed at the top and opened at the bottom is presented. Numerical simulation is performed using the restricted domain model and extended domain model. The outer wall and top wall of inner cylinder are insulated. The outer w...
Abstract: Numerical simulation was carried out by using fluid Volume function（VOF） method to study the equal-sized head-on binary droplet collision in steam separators. The typical coalescence and reflexive separation with low, middle, high We, were investigated. Droplet shapes during the collision process we...
Abstract: Intermittent flow behavior in a vertical channel under low-pressure conditions is experimentally studied using a small scale experiment facility in the present study. The effects of different factors on the flow characteristics are investigated in detail. The results reveal that the steam eruption o...
Abstract: Cavity flooding is an important severe accident management measure for the in-vessel retention of a degraded core by external reactor vessel cooling in advanced PWRs. A code simulation study on the natural circulation flow in the gap between the reactor vessel wall and insulation material under cavi...
Abstract: A single bubble growing model is established under subcooled flow boiling conditions in vertical rectangular narrow channel to numerically investigate the bubble growth. The model combines interface evaporation/condensation based on molecular dynamics and microlayer evaporation. The phase change mod...
Abstract: Effect of fuel oxidation on fission product diffusional release is analyzed, and it is concluded that the vacancy increase due to the fuel oxidation has greater effect on the enhanced fission product release than the temperature increase due to the degradation of fuel thermal conductivity. The fissi...
Abstract: Corrosion fatigue crack-tip plastic zone of Inconel 690（TT） was investigated, and the effects of crack-tip plastic zone and load ratio on the corrosion fatigue cracking in the simulated pressurized water reactor environment were studied. The accelerating effects of the simulated pressurized water re...
Abstract: Hoop tensile test is performed on N36 zirconium tube ring specimen at 350℃ to study the iodine induced stress corrosion cracking（I-SCC） behavior of zirconium tube in iodine gas environment, and the stress-elongation curve in partial pressure of iodine gas as 102 Pa,103 Pa,and 104 Pa separately are d...
Abstract: The effects of Cl- and Cu2+ on the stress corrosion cracking（SCC） of Alloy 690 made in China were investigated using the slow strain rate tensile（SSRT） test. The surface and cross section morphologies of tested specimens, as well as the fractographs, were observed by 3D measuring laser microscope an...
Abstract: The effect of circumferential stress and thermal cycles on the hydride orientation factor（Fn） of N36 zirconium alloy tubes after hydriding has been studied, and several deviations during the test and the uncertainty of measurement for Fn has been mainly analyzed and computed. The results show that, ...
Abstract: In order to solve the problems of aging of core cooling monitoring system, and the unstable work and the flash failure alarm of CCMS due to unavailability of some old parts in Daya Bay Nuclear Power Station, the modification of the whole upgrading program is proposed. The design of new CCMS using lo...
Abstract: The paper conducts the secondary side thermal economy analysis of China improved 3rd Ring Rd Pressurized Water Reactor（CPR1000） nuclear power plant according to the principal method of thermal system calculation. The stream generator of Ling’ao nuclear power plant（phase II）, as an example, is calcul...
Abstract: The technology improvement for the reactor pressure vessel on Ling’ao Phase II Nuclear Power Station is given. This paper presents the description of the integrated core shell, integral reactor pressure vessel top cover, the control of irradiation sensitivity element content, co resident content red...
Abstract: The new seal structure was designed to satisfy the function of thermocouple column assembly and the reactor structure. This seal structure uses the packing graphite ring and adopts the self-sealing principle. Cone angle is brought to the seal face of seal structure which is conveniently to assembly ...
Abstract: The purpose of this study is to develop the tritium trap for LWR fuel element irradiation test with power transient, to purify the 3He gas from tritium produced by neutron capture. Titanium sponge particles were selected as the storage materials. The design of prototype vessel was determined by fact...
Abstract: This paper analyzed the present passive technology in nuclear power plants, and based on the special requirement on the application of the passive methods used in the nuclear power plants under the marine conditions, the theoretical research, experimental technology, design technology, equipment tec...
Abstract: Being aimed at the problems that it is difficult to recognize effectively the faults of core barrel rupture and fall off of core barrel fasteners parts, a method of the wavelet packet energy analysis and DSm T is proposed. By using the wavelet decomposition and reconstruction method, the fault signa...
Abstract: The nuclear power plants are possible to suffer the core uncovering damage due to the heterogeneous boron dilution which is out of the design basis. This paper analyzes the mechanism of criticality accident caused by the heterogeneous boron dilution, and study the measures to prevent the erroneous d...
Abstract: This paper comprehensively analyzes the impact on the nuclear power plant security when LCA / LCB loses the power. When LCA loses the power, the normal boronization of the reactor coolant is unavailable, only the direct boronization can be used; the normal discharge, excess discharge and low pressur...
Abstract: According to the U-shaped tube breaking accident of steam generator（SGTR）, this paper designs a fault-diagnosis expert system based on the alarm triggering. By analyzing the fault mechanism of SGTR accidents, the fault symptom is obtained. The parameters of the belief rule are set up based on the si...
Abstract: During the initial start-up of HYH NPP unit 1, spike currents occurred in intermediate range channel of RPN system and reactor trip was triggered. After analyzing the operation principle of intermediate range channel and site inspection, and doing simulating test, the root cause was fixed on the bug...
Abstract: With the extension of the operation period, the characteristics of narrow range temperature probe will be drifting and aging in CPR1000 units. At the same time, the change of thermal hydraulic characteristics factors will also lead to the unreasonable setting of the parameters of average temperature...
Abstract: Based on the collection and statistical analysis of the radiation monitoring instrument calibration data, and taking the typical GIM204 gamma dose rate monitoring device as an example, the feasibility is demonstrated by the experience feedback method, to adapt to the implementation of the refueling ...
Abstract: Several factors can influence the activated charcoal adsorption coefficients of gaseous radwaste treatment by activated charcoal delay beds in nuclear power plants. This paper analyzes the effects of temperature, relative humidity, gases concentration and gases flow rates on the activated charcoal a...
Abstract: Service water system operation requirements and circulate water system maintenance needs are analyzed, and it is determined that the circulate water system maintenance will result in the availability of service water pumps. Solutions are proposed to resolve the conflicts between the circulate water ...
Abstract: In order to improve nuclear power plant safety review work, NNSA imported reactor thermal hydraulic best estimate code TRACE from NRC. In this paper, the NPQJVC two-loop PWR thermal hydraulic model is setup and LBLOCA is simulated using TRACE code and engineering modeling assistant code SNAP. The re...
Abstract: Using MELCOR, the numerical simulation of steam condensation inside vertical tube in the presence of noncondensable gases is carried out. Calculated results are compared with Kuhn’s experimental results. Generally the agreement is satisfactory except that the heat transfer process and condensed film...
Abstract: In this paper, the analyses were carried out on Ling’ao nuclear power station phaseⅡ to study the consequence of the loss of coolant accident when the homologous characteristic curves and free volumes of the reactor coolant pump changed. Two different pumps used in the analysis were 100D（employed on...
Abstract: The mechanism of the vane-type bubble separator developed for Thorium Molten Salt Reactor was investigated experimentally and numerically. The experimental phenomena and flow field obtained by the CFD software of Fluent were compared to analyze the process of the bubble coalescence and merging into ...
Abstract: An integrated CFD model was built in which the main components of the first loop are included.The intermediate heat exchanger,decayed heat exchangers,reactor core and main pump are simulated by the method of additional source term.The integrated model is closer to the real situation as there are not...
Abstract: COSINE is the first software package for the nuclear power plant design and analysis developed in China. The system analysis code of COSINE has two versions, one is the conservative model version and another is the best-estimate model version. According to the latest evaluation model development and...
Abstract: A numerical simulation is carried out to investigate the influence of shroud in lower plenum on flow field. The geometrical model and boundary conditions in the simulation are the same as the integral hydraulic experiment which based on domestic CNP1000 nuclear power plant. CFD method is adopted, th...
Abstract: With reference to the parameters of integral natural circulation test facility OSU-MASLWR, the system analysis code RELAP5/MOD3.3 was applied to investigate the thermal-hydraulic characteristics. Transient safety studies were done for loss-of-coolant accidents within the containment. The results sho...
Abstract: The water property will have a big variation in the pseudo-critical region under supercritical conditions and largely impact the heat transfer and fluid flow characteristics of the supercritical water. The water property data will directly affect the credibility of the numerical prediction results. ...
Abstract: The bubble hydrodynamics characteristics such as the bubble rising velocity, bubble shape and drag coefficient was studied. The bubble was generated using a hemisphere cup to collect specific volume and released to the still water manually. The bubble motion was captured by high speed camera. The pa...
Abstract: Typical severe accident scenarios are calculated to obtain the characteristic parameters of the molten pool in the lower vessel plenum, based on the MELCOR model for small module reactors. The indigenous CISER code is then used to analyze and validate the effectiveness of the cavity injection and co...
Abstract: Based on Eulerian two-fluid framework and non-equilibrium subcooled boiling model, the numerical model is established to simulate the subcooled boiling. This model is used to simulate the subcooled flow and CHF of DNB type in uniformly heated tubes. The numerical model is proved correct by comparing...
Abstract: The supercritical water cooled fast reactors worked at such harsh condition with high temperature and high pressure, huge hydrogen balance pressure and thermal shock can result in a great loss of hydrogen. The released hydrogen would be out of control under accident situations. Keff, conversation ra...
Abstract: Based on the comparative analysis of the current DCS software evaluation methods, the authors adopted the BTP7-14 of NUREG-0800 as the reference standard for evaluating AP1000 nuclear power plants. An overall framework based on Bayesian Belief Network（BBN） for reactor protection system software reli...
Abstract: According to the nuclear safety regulations and guidelines in China, the information of the IAEA and the NRC, this paper discusses the origin, purpose, method and report of the management review, the basic concepts and requirements. In order to identify the difference between the management review a...
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