Abstract: The paper firstly proposes a coupling resonance method in which subgroup method is employed in the serried peak energy region, and wavelet expansion method is employed in single peak energy region. The original subgroup model and wavelet expansion model are improved and coupled through the calculati...
Abstract: Perturbation calculation can be used to estimate the changes of effective multiplication factor caused by perturbed system parameters, and is the fundamental of reactor sensitivity and uncertainty analysis.With the development of computer techniques and the increasing needs of new concept and comple...
Abstract: Inventories of radioactivity in Xi’an Pulsed Reactor（XAPR） are calculated, with the assumption that XAPR is continuously or intermittently operated at full power of 2MW until the fuel rods archive the design burnup. With a conservative releasing model, the biggest inventory 4.13×1016 Bq was selected...
Abstract: Within the pressure range from 11 to 19 MPa, mass velocity from 700 to 1300 kg/（m2·s）, and inner wall heat flux from 200 to 1000 k W/m2, experiments were performed to investigate the heat transfer characteristics of water flowing in subchannel with square distribution in SCWR. The subchannel was for...
Abstract: The experimental apparatus was designed and made up of isotropous particles（pebble） in porous media. All the pebbles were unordered accumulation. The experimental research on the flow characteristics of nitrogen-water two-phase flow in channel was conducted. The porous media channels were consisted ...
Abstract: Wire wrapped rod bundles were generally adopted by SCWR fuel assembly design. The wire wraps may have complicated impact on the thermal hydraulic behaviors of the rod bundle. In this paper, some improvements have been made on the geometry identification of the wire wrap model based on the subchannel...
Abstract: By using RELAP5 and MELCOR, transient behaviors of containment and PCS were investigated. The Influences of various parameters, such as pressure, condenser area and loop height were also studied. The results show that the heat in the containment can be effectively removed by PCS in a period of accid...
Abstract: Heat pipe has been widely used to cool the space nuclear reactor core. Flow in the reactor heat pipe, which is characterized by the evaporation and condensation of its inner fluid, is remarkably different from the tube flow, thus the variable mass flow, axis velocity and radius velocity must be take...
Abstract: This paper studies the effects of sintering temperature and thorium content On the density of（Th,U）O2 pellets. The activation energy for sintering（Th,U）O2 pellets were calculated, the movement and transplantation were analyzed by using Scanning Electron Microscope（SEM）. The results show that the den...
Abstract: The co-precipitate of Thorium and Uranium（AUTh C） was prepared by co-precipitation technique, the（Th,U）O2+x powder was obtained by the decomposition and reduction of the AUTh C. The decomposition process of AUTh C was analyze by DTA-TG, the specific surface area of（Th,U）O2+x powder was measured by B...
Abstract: Single temperature evaluation and multi-temperature analysis about the Pre-Cracked Charpy Specimens PCVN and 1/2 PCVN specimens of Chinese RPV steels were done. Both of the reference temperature T0 of PCVN and 1/2 PCVN specimens were calculated. The results were corrected by the size criterion const...
Abstract: The irradiated surveillance specimens are welted on the inner surface of WWER1000 reactor vessel. The specimens are withdrawed by melting and cutting the welding joint. The radiation sources and radiation level is analyzed in order to evaluate the radiation risks and choose the radiation protection ...
Abstract: The Leak Before Break（LBB） concept, as an important feature of the third generation nuclear power technology, is widely used in the high-energy piping design in nuclear industry. However, for some historical reasons, the application of LBB concept in China lagged behind compared with that in the dev...
Abstract: The Reactor Pressure Vessel（RPV） upper internals support columns are subjected to high speed liquid impact in the cross flow field during the operation conditions at nuclear power plants. With the cross flow impact, the vibratory behavior of the RPV upper internals support columns may occur. The vib...
Abstract: The primary system seismic analysis was performed to study the influence on primary system seismic loads with different reactor coolant pump by using ANSYS software. The results show that the stresses evaluation of the primary pipe for two reactor coolant pump models are meet code requirement. Theas...
Abstract: Modal analysis of the containment spray pump is carried out by using ANSYS program, and structural natural frequencies and modes of vibration can be obtained. After that, the dynamic characteristic test is performed for the containment spray pump. The comparison between modal analysis results and te...
Abstract: Based on the mechanical and irradiation properties of beryllium, the irradiated beryllium component stress analysis was proposed, in which the mechanical stress, thermal stress and irradiation swelling induced stress and the load combination in the operation conditions are considered,, and also the ...
Abstract: It introduces the Anticipated Transisents Without Trip（ATWT） in this article,and analyzes the diversity and independence of ATWT mitigation system, and discusses the problems faced in the design of ATWT on the basis of relevant law and regulations.
Abstract: Making use of MELCOR program, the blackout accident of small reactor is simulated and analyzed in the paper, the result of which is provided to the atmospheric dispersion software MACCS, and the radioactive consequence is calculated and analyzed in a coastal area. Combining with the criteria for the...
Abstract: Jeffreys priors for gamma and beta distribution was derived after adopting Jeffreys prior theory.Furthermore, the expressions were given to estimate the hyper parameters of generic data distribution using B ayesian approach. Compared to the results using classical statistics theory, the data process...
Abstract: This paper describes the methodology and parameter definition of dΦ/dt correction channel of CPR1000. These correction parameters have been studied essentially by combining with real nuclear power plant design parameters and using best-estimated transient analysis code CATIA2. According to compariso...
Abstract: During the fabrication and tubing of the tube bundle for steam generator, some local deformations in the U-bend area might occur, which will result in a smaller gap or even contact between tubes. According to the design principles for tube bundle, taking CPR1000 steam generator（Type 55/19B） as the a...
Abstract: The Reactor Coolant Pumps（RCP） of AP1000 nuclear power plant are the canned motor pump. Because of the restriction of the RCP motor design parameter and operation mode, the Variable Frequency Drive（VFD） shall be used to meet the operation and technical requirements. This paper studies the power supp...
Abstract: In the production and use of radioactive fuel process, it is an important process to measure the burn-up level for fuel element in accurate and efficient way. At present, the automatic operation of burn-up measurement of plate-type fuel element is unimplemented, and it applies only to single-point m...
Abstract: The reactor control rod drop time is an important parameter for the safety analysis and significant to the power plant safe operation. In order to get the control rod drop time history, in this paper, the kinetics equation and calculation Method is established. The complicated fluid and mechanical f...
Abstract: The standard architecture and overall requirements of the equipment qualification for Class1 E digital instrumentation and control（I＆C） system are discussed. Based on the comparison of NUREG 0800 and RCC-E technical specification, the technique of equipment qualification for Class 1E digital I＆C sys...
Abstract: Aiming at the titanium alloy of new pattern steam generator unit, this paper proposed the use of AE technology to monitor the material performance during the manufactory. Using the AE monitoring system to monitor the whole process of the elongate test of standard tensile sample and analyze the obtai...
Abstract: This research is aimed to defect location problem of X-Ray test technology on a new pattern steam generator unit bilateral welding, proposed a scheme that used vertical and tilt Radiographic inspection technology to locate disfigurement and affirmed validity of searching scheme by examination. The t...
Abstract: After using ETA as the p H adjustment agent in secondary Circuit of Qinshan 320 MWe PWR plant in place of ammonia, the p H of Moisture Separator Reheater（MSR） drainage and Stream Generator（SG）blowdown water are obviously increased, so that the corrosion conditions are improved, such as: the corrosio...
Abstract: This paper introduces the function of TNPS refueling machine, the structure of rod cluster assembly protective jacket, and the condition of functionality recovering. It also describes some problems found when fuel assemblies and rod cluster assemblies are rearranged and replaced during refueling out...
Abstract: For analyzing the hydraulic performance and air inlet problem of passive containment cooling system（PCS）, the software FLOWMASTER is used to establish an one-dimensional hydraulic model, and using it, the PCCWST water supply flow rate for 72 hours after accident is calculated; The two-dimensional FL...
Abstract: In the domestic and abroad standards, the grounding capacitive current limitation in the non-grounding electric auxiliary system is less than 10 A. Limiting capacitive current in the standard aims to speed up the arc extinguishing, to reduce the duration of arc over-voltage, but not to prevent the a...
Abstract: Wavelet Analysis is a new signal analysis theory, but in the way of the engineering application,the wavelet analysis has the problems such as frequency confusion and amplitude frequency offset distortion.This study makes the use of the frequency compensation, an improved algorithm of wavelet packet,...
Abstract: In order to obtain the flow state during sewer condition in Reactor and CRDM Sewerage system（RSE）, this paper analyzes the 3-D steady flow in RSE by using Computational Fluid Dynamics（CFD） method. In the premise that the pressure drop of the RSE is known, the mass flow rate, the velocity and the typ...
Abstract: Based on the reactor protection system of a certain type of digital I＆C system for a nuclear power plant, this paper analyzes its structure and functions, and puts forward the requirements of the graphic automatic modeling. It develops the dedicated accessorial software for reliability analysis base...
Abstract: The flow conditions and the tracks of sludge particles around the sludge collector in a typical U-tube recirculating steam generator are studied by a Computational Fluid Dynamics method. To evaluate the main factors affecting the deposition process of sludge particles, a Lagrangian Particle Tracking...
Abstract: In order to analyze the effect of common cause failure（CCF） on average probability of failure on demand（Pavg） calculation, fault tree models of a normal excitation 1oo2 system are established. The Pavg without regard to CCF and Pavg with regard to CCF（use β factor model） are both calculated. By comp...
Abstract: Flow regime transition under constant pressure drop rate in rectangular channel is investigated by theoretical and experimental study. Laminar velocity distribution and the method to determine the critical Reynolds number is obtained by theoretical study. The factors that affect the critical Reynold...
Abstract: The characteristics including dissociation, vapor-liquid distribution, thermal decomposition,compatibility with materials of ethanolamine（ETA） used in secondary system of nuclear power plant（NPP）were investigated by the laboratory research and full-scale testing at Nuclear Station. The results show ...
Abstract: In the paper, the chemical and physical characteristics of sodium aerosol particles as well as factors that influence the sedimentation rate of sodium aerosol during its transport are analyzed. Besides, a simplified model is given to calculate the sedimentation rate when aerosol getting through the ...
Abstract: RIC manual valves and seal assemblies made of austenitic stainless steel were wrongly degreased with tetrachloroethylene by the manufacturer. Chloride ions（Cl-） were produced during the pyrolysis of tetrachloroethylene,leading to the risk of stress corrosion cracking（SCC） due to the remaining Cl-. T...
Abstract: This paper gives a detailed introduction about the development demand, development method,design details and implement process of the management application information platform（DORP）. As some unique ideas such as container, reuse, combination are adopted in the design of DORP, the development of th...
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Sponsored by: Nuclear Power Institute of China
Editorial Office: Nuclear Power Branch of China Nuclear Society
