Abstract: The neutronics characteristics of the square assembly that employs the homogenous thorium-uranium fuel have been analyzed and evaluated, and the numerical results show that the infinite multiplication factor of fuel assembly decreases more slowly with the increasing burnup. In other words, better re...
Abstract: Based on the adjoint transport technology, the ex-core detector response function under the full power operation of one third-generation reactor is calculated by using the two-dimension SN code. Calculation results are compared with the original data, and the radial weighting factors would not excee...
Abstract: The Station Blackout Accidents（SBO） analysis is performed by CATHARE for passive reactor heat removal system（PRHRS） test facility and ACP100 respectively. The results show that the PRHRS test facility, which is designed according to the modified Ishii natural circulation scaling law, is capable of r...
Abstract: It is important in the reactor research and design to choose the typical lattice, which could represent the channel shape and thermal-hydraulic performance of the prototype assembly. In this study, the effect of bundle scale on thermal-hydraulic performance has been analyzed by numerical simulation ...
Abstract: Experimental investigation on flow resistance coefficient for the tight arrangement spiral-fin fuel assembly was performed. Results show that the inlet temperature has no effect on the flow resistance coefficient. The deviation between the proposed correlation and experimental data is less than 1%. ...
Abstract: Looking for high-performance and minimized heat exchange tube is one of the way for improving the performance of Once-through steam generator（OTSG）. This paper introduced the thermal-hydraulic experimental research on a new type heat exchange tube with internally revolved rib. The test system and th...
Abstract: In this paper, the numerical simulation of the three dimensional flow fields is performed for the surge line of the nuclear power plant. The simulation incorporates the coupling effect between the solid pipes and the liquid coolant and the conjugate effect between the heat transfer and fluid flow. T...
Abstract: Experiments were carried out in a rectangular loop to study the characteristics of supercritical carbon dioxide natural circulation. The influence of pressure and temperature difference on the mass flow rate was investigated and the effect of geometric of test loop was also preliminarily studied. Re...
Abstract: The power transient model and reactivity feedback model on transient thermohydraulic characteristics analysis of Heat Pipe Segmeuted Thermoelectric Module Converters（HP-STMCs） cooled space reactorcore were built by using CFD interface UDF, and the HPSR core transient analysis code SNPS-FTASR was dev...
Abstract: Based on the boundary layer stripping mechanism, the hydrodynamic fragmentation process of fuel and coolant interaction（FCI） has been studied. With theoretical modeling and experimental correlation, semi-empirical equations which can predict the mass fragmentation rate and average size of fragments ...
Abstract: In this study, based on the phenomena and characteristics of LOCA for the small modular PWRs, the mechanism for the occurrence of Peak Cladding Temperature（PCT） was analyzed, and the effects of accumulator（ACC） design on PCT and system depressurization were studied. It is shown that the accumulator ...
Abstract: The Chinese criteria for protective action, intervention level, operational intervention level and off-site emergency zones are compared with IAEA guideline in the paper.The suggestions are put forward to implement the intervention in Chinese NPP emergency exposure situations.
Abstract: Sometimes, the emergency operation Procedure implemented after the accident is related to the emergency IC and EAL. However, the basis of the emergency IC and EAL is the indications and parameters representing plant safety state, and the basis of the EOP is the events and accidents, and sometimes th...
Abstract: The on-line monitoring and forecasting techniques for the nuclear power plant reactor coolant system are studied. Based on the analysis of the characteristics of the reactor coolant system components and fault characteristics, multi-state variable estimation techniques（MSET） and sequential probabili...
Abstract: The paper proposes a new control strategy to apply in the field of pressure controller of once-through steam generator. The strategy is distributed and multiple input and output coupling Artificial immune control strategy which is based the thought of decentralized control of the distributed control...
Abstract: By using the traditional spectral line smoothing methods, improper filter parameter settings or a high frequency of smoothing will cause the spectral line distortion. To address this problem, the fast Kalman filter is used to implement the recursive least squares method according to the adaptive fil...
Abstract: Reliability data is the basis of probabilistic safety assessment in NPPs. The parametric empirical Bayes models would underestimate the uncertainty of estimated parameter in the case with few failure data. Kass-Steffey adjustment could use Taylor series expansion to correct the posterior variance. T...
Abstract: A method combining Markov and convolution is provided in this paper. The power recovery scenario after station blackout is used to demonstrate the method in detail. The analysis results show that the method can efficiently solve the time interdependence issue, thus eliminating unnecessary conservati...
Abstract: CFD software is applied to analyze the hydraulic characteristics on the main check valve flow model about multi-loop reactor. The outlet non-uniform flow of reactor coolant pump is used to calculate the hydraulic moment of the valve under the full-open condition. By analyzing the key structure facto...
Abstract: Based on the running experience for 100 D Main Coolant Pump, its typical abnormal vibration phenomena is studied, and a vertical rotor-bearing system dynamics theory is established to analyze the vibration characteristics of the rotor. It can conclude that as for the conference of vertical construct...
Abstract: Because of the origin design for control logic of entrance isolation valve in RRA system was not conform to the single failure criterion, the improvement scheme, which would be added two sets of pressure transmitter, has been raised. The effect of RRA system and the damage of reactor core have been ...
Abstract: Function expressions of kinematic pair force with latch dimensions, friction coefficient, link angle and external load was obtained by theoretical analysis, and the expression was verified by the motion analysis software. Key parameters of kinematic pair were confirmed,and their effect trends with f...
Abstract: A model enabling all different flow state lubrication performance simulation and analysis for water-lubricated thrust bearing is presented, considering the temperature influence and elastic deformation. Lubrication state in the model is changed directly from laminar lubrication to turbulent lubricat...
Abstract: Experiments and DEM simulation have been conducted to investigate the granular flow through a new type of sphere discharge valve. The new sphere discharge valve was based on the principle of angle of repose. The glass sphere was used in the granular discharge experiments.Experimental results showed ...
Abstract: In nuclear power plants, iodine adsorption efficiency test is used to check the iodine adsorption efficiency of the iodine adsorber. The iodine adsorption efficiency can be calculated through the analysis of the test sample, and thus to determine if the performance of the adsorber meets the requirem...
Abstract: The RCP of Fangjiashan NPP is much different with that in other nuclear power plants in China. This paper firstly introduces the generational of RCP, then expound the problems and ways in commission. The main problems, such as the large vibration of pump shaft, the maladjustment of main coolant pump...
Abstract: Nuclear power plants gradually adopt the long-term fuel cycle, the power density of the reactors is increasing and the level of burnup is higher. It is more complex and difficult to control the primary coolant chemistry. The water chemistry of enriched boric acid in primary coolant was calculated. R...
Abstract: False alarm problem of radioactive iodine activity monitor during commissioning in nuclear plant is analyzed and studied. Results show that the instrument background noise, ambient gamma radiation field and other non nuclide measurement statistics will cause the measured value distortion; the using ...
Abstract: Based on the cleaning of the secondary side in High-Temperature Gas-cooled Reactor（HTR-PM） steam generator. the compressed air blowing technology are proposed in this paper. Through the analysis on the flow behavior of steam-water two-phase or one-phase in helical coils of the secondary side in the ...
Abstract: Using RCV system hydraulic model, the feasibility of increasing purification flowrate during plant shutdown oxygenation of M310 units is analyzed, and a basic engineering modification for this item is provided. The result indicates that the purification flowrate increase from 27.2 m3/h to 40 m3/h, a...
Abstract: The chemical effects for the recirculation sump filter blockage of CPR1000 Nuclear Power Plant（NPP） under Loss of Coolant Accident（LOCA） is studied. In chemical effects evaluation, simulation experimentation is adopted. The result indicates that the effect of chemical effect on the emergency recycle...
Abstract: The passive safety system was applied to the fusion-fission hybrid energy reactor and a RELAP5 model was developed to represent the primary loop, partial secondary loop and the passive safety system components. The transient calculation and research were conducted for stuck pump accident, the SBLOCA...
Abstract: In-Vessel Retention-External Reactor Vessel Cooling（IVR-ERVC） is a key severe accident management strategy, and the present assessment method on the effectiveness of IVR is mainly based upon the lumped parameter（LP） model. With related regulations considered, four severe accident scenarios were sele...
Abstract: Turbulent flows in a rod bundle are important field for the nuclear reactor fuel assembly since the flow mixing in a sub-channel or between sub-channels can significantly modify the heat transfer performance. A five beam three dimension Laser Doppler Velocimetry（LDV）system is applied to measure the ...
Abstract: Natural circulation characteristics in symmetrical loops under rolling condition were investigated theoretically and experimentally. Rolling experiments with a zero power load show that angular acceleration causes the fluctuation in branch flow channels, but has no influence on the middle channel. F...
Abstract: The incline and swing effect on natural circulation of floating nuclear power plant under site black out（SBO） accident is studied using self-developing marine condition system code RELAP5/MC. It shows that,for floating nuclear power plant under marine condition, the pressurizer fluctuating flow rate...
Abstract: In order to improve the computational efficiency and reduce the memory usage of the function in the Reactor Monte Carlo code RMC to compute the effective multiplication factor（keff） sensitivity coefficients with regard to nuclear data, two parallel strategies which are based on two ways to estimate ...
Abstract: It is difficulty for the MOC method based on Cell Modular Ray Tracing to deal with the irregular geometry such as the water gap between the PWR lattices. Hence, the neutron transport code NECP-Medlar based on Assembly Modular Ray Tracing is developed. CMFD method is used to accelerate the transport ...
Abstract: To study the height effect of the pebble flow dynamics, a 2-D pebble-bed experimental system for High Temperature Gas-cooled Reactor（HTGR） has been established based on the similarity criteria to study the pebble flow by using the marking pebble method. The characteristics of mean stream line, inner...
Abstract: The Compressive creep behavior of as-cast Ag In Cd alloy with and without tin（Sn, 3wt%） was investigated by using the special modified apparatus on RDL50 creep tester at 300~400℃and compressive stress was in the range of 12~30 MPa.The relationship among temperature, stress and steady strain rate has...
Founded in 1980 (
bimonthly
)
Sponsored by: Nuclear Power Institute of China
Editorial Office: Nuclear Power Branch of China Nuclear Society
