Abstract: The main function of the rod position detector power supply in the nuclear power plant is to provide the sine wave current for the detector primary windings. The output accuracy and load variation response have effects on the rod position measurement accuracy. In order to improve the above performan...
Abstract: The development of the software CORCA-3 D and CORCA-K developed on self-reliance involves the correctness verification of core diffusion numerical calculation. In order to improve the efficiency of R&D, based on the core module named TRIVAC in DRAGON, the automatic contrast verification scheme o...
Abstract: The monte-carlo neutron-photon coupled transport program（MCNP） is used in reactor shielding design to calculate the neutron flux rate of reactor pressure vessel and reactor components to evaluate the neutron irradiation damage to structural materials.In the calculation of such fixed source problems,...
Abstract: Fluid induced vibration of the angle stop valve was obvious which brings some difficulties for controlling the vibration and the noise in the cooling water system of some nuclear devices. For reducing the vibration, the fluid induced vibration characteristics of both the angle stop valve and oblique...
Abstract: The sovlving methods of depletion equation is researched, including Taylor method,Pade method, Scaling and squaring method（Scale）, Eigenvectors method（Eig）, Chebyshev rational approximation method（Cram）, Lagrange interpolation method, Newton interpolation method,Vandermonde method and Krylov subspac...
Abstract: The point kinetics is very important to the safety of the reactor operation. However,these equations are stiff, with very small time step for solution. The diagonally implicit Runge Kutta（DIRK）with exponential transformation is studied for point kinetics. It keeps the advantage of diagonally implici...
Abstract: Static buckling load is an important concept for assessing the structural performance of the spacer grid. The finite element analysis（FEA） of static critical buckling load for 3×3 spacer grid has been investigated with analyzing the influence of grid structural characteristics. Results show that the...
Abstract: The ANSYS was employed in the interference connection design for the reactor vessel internals of ACP100. Compared with theoretical formula and the results of finite element method（FEM）, the FEM for the design of interference connection was acquired, and the FEM was used to study the stress condition...
Abstract: Reactor coolant pump（RCP） is one of the key devices in the reactor coolant system in nuclear power Unit. The safety and stability of the RCP concerns the safety of the nuclear power plant. HPR1000 is the third generation nuclear power plant developed by China on self-reliance,with severe requirement...
Abstract: It is necessary to use the computed fluid dynamic（CFD） method to study the problems considering the U-tube distribution, such as the reverse flow in the steam generator. But it is difficult to model all the U-tubes in a steam generator because of the huge number of the U-tubes and the limited capabi...
Abstract: This paper introduces the design requirement and characteristics of the cable shearing tool for the temperature-measuring element in pulsed reactors. Accrording to the characteristics of the cable shearing and the man-machine engineering theory, a shearing structure scheme is proposed, in which the ...
Abstract: To determine the most appropriate stage of ultrasonic test for reactor pressure vessels（RPV） steel forgings, this paper confirmed that RCC-M requires the ultrasonic test be done after final finishing, and analyzed the rationality of the requirement based on the ultrasonic examination mechanism, refe...
Abstract: The study was performed based on numerical CFD simulation by means of dynamic meshing. A CFD model was established to reproduce the valve opening behavior, which means that a dynamic valve disc model has been built using the trimmed volume mesh and the deformable mesh coupled with 1 D freedom model ...
Abstract: The reactor coolant system simulation model for the two-loop nuclear power plant is established using the thermal hydraulic analysis software Flowmaster. The power operation steady condition, the bias-loop operation steady condition during startup/shutdown reactor, the pump coastdown operation trans...
Abstract: Bottom nozzle, used to support and locate, is an important structural component of CF3 fuel assembly. FEM and load test method were adopted to study the mechanical properties of CF3 fuel assembly bottom nozzle. The result shows that the stress on every condition meets the requirement of the ASME cod...
Abstract: Small PWR has adopted the suppression tank and the steel containment with outside pool to mitigate the containment pressure and temperature increasing after a relevant accident. The features of suppression and heat transfer are essentially different from those of a conventional PWR.This paper studie...
Abstract: The full-range simulator in Tianwan nuclear power plant is mainly used for the training and authorization of the operators in the master control room. Since it is an important tool and means for operator training, its consistency with the main unit and its availability shall be guaranteed. In order ...
Abstract: Traditional nuclear power plant（M310） adopts the bypass measurement method to measure the key safety parameter, i.e., the reactor coolant temperature, but this method cannot satisfy the requirement of the 3 rd generation nuclear power for the complicated process loop, large amount of connection on t...
Abstract: The code developed on self-reliance was used to perform the conceptual design of the sodium cooled standing wave reactor. To reduce the power peak of the inner core, the radial partition design was used. To control the radial power distribution, the outward fuel shuffling strategy was adopted. MCNP-...
Abstract: In order to accurately predict the critical heat flux（CHF） in pressurized water reactor core fuel assembly, the effects of spacer grids, cold walls and non-uniform heat flux in rod bundles on CHF are analyzed. Simultaneously, six CHF mechanism models based on different physical hypothesis are compar...
Abstract: In this paper, one ship-type Floating Nuclear Power Plant（FNPP）, which is fixed by multi-point anchor chain, was studied. The loads applied on FNPP was calculated and analyzed under various kinds of external forces, such as wind, wave, current and ice, and under the sea conditions encountered in one...
Abstract: The leakage of the pressure boundary of the nuclear power plant is an important operation event. The response and treatment after the occurrence of abnormal events is focus on the safety management of the nuclear power plant. Based on the treatment of the leak point on the extension branch pipe of t...
Abstract: The applications of the defense in depth in the design of the irradiated fuel water pool storage, I&C system, electrical system, and the protection systems for internal and external hazards of the nuclear power plant are reviewed in this paper. Base on the study of the newest standard and codes,...
Abstract: The optimization study is carried out for the disadvantage of cavity injection and cooling system（CIS） in HUALONG 1 plant, when dealing with serious accidents, and the new system configuration and operation of CIS is presented, including adopting control valves to control flow of different condition...
Abstract: After the accident in Fukushima nuclear power plant, it is more often to adopt a combination of active and passive accident mitigation systems in Chinese 3 rd generation nuclear power units, compared with the 2 nd generation plus nuclear power unit（M310）. Chinese 3 rd generation nuclear power units ...
Abstract: This paper mainly studies the standard system of the third generation nuclear power technology HPR1000, and emphasizes on the top level design of the standard system. Firstly the paper summarizes the current standard situation adopted in HPR1000, specifies the standard system study area, and primari...
Abstract: An effective emergency response system is the basis of accident management in case accident. The accident of Fukushima Daiichi Nuclear Power Plant suggests that extreme external hazards may affect the normal emergency system of the nuclear power plant, which results in the difficulty of accident mit...
Abstract: The four methods are used to simulate the plate heat exchanger in Units 1 and 2 in Fuqing Nuclear Power Plant, i.e., the criterion number heat exchange formula, HTRI heat transfer factor empirical formula, Matin heat transfer factor empirical formula and A. Muley heat transfer factor empirical formu...
Abstract: PIPESTRESS program is used to analyze and evaluate the nuclear safety class 1 and class 2 piping model with elbows, and the influence of two calculation methods of the separate calculation and the restart calculation is compared. The research shows that there is a deviation in the result of the sepa...
Abstract: In this paper, the method of planeness deviation analysis in the construction stage of the bottom steel liner is adopted to calculate the bottom steel liner of different sizes, the limit value of the planeness deviation of the bottom steel liner of different sizes is obtained. Calculation results ar...
Abstract: In this paper, the design of a polar crane bracket is optimized using EXCEL and ANSYS. Based on the so-called fiber model, ABAQUS and MATLAB were used to simulate the mechanical behavior of the embedded parts under the combined action of axial force and bending moment. This design method can quickly...
Abstract: At present, the domestic AP1000 nuclear island dome is assembled in the surrounding area of the nuclear island, and it is restricted by the site and traffic constraints, and the program is not universal. According to the needs of the whole assembly, based on the dome transport bracket, road transpor...
Abstract: Emergency Action Level（EAL） is one important tool to determine the emergency classification level in nuclear emergency response. Because of its design characteristics, the risk spectrum characteristics of a large advanced passive light water reactor are different with that of the nuclear power plant...
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