Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy

Beijing, China

Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy

Beijing, China
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He S.,North China Electrical Power University | Zang Q.,North China Electrical Power University | Zang Q.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | Zhang J.,North China Electrical Power University | And 5 more authors.
Radiation Protection Dosimetry | Year: 2017

Point kernel integration (PKI) method is widely used in the visualization of radiation field in engineering applications because of the features of quickly dealing with large-scale complicated geometry space problems. But the traditional PKI programs have a lot of restrictions, such as complicated modeling, complicated source setting, 3D fine mesh results statistics and largescale computing efficiency. To break the traditional restrictions for visualization of radiation field, ARShield was developed successfully. The results show that ARShield can deal with complicated plant radiation shielding problems for visualization of radiation field. Compared with SuperMC and QAD, it can be seen that the program is reliable and efficient. Also, ARShield can meet the demands of calculation speediness and interactive operations of modeling and displaying 3D geometries on a graphical user interface, avoiding error modeling in calculation and visualization. © The Author 2016. Published by Oxford University Press. All rights reserved.


Qi S.,North China Electrical Power University | Qi S.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | Zhou T.,North China Electrical Power University | Zhou T.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | And 7 more authors.
Progress in Nuclear Energy | Year: 2017

Ledinegg flow instability of two-phase natural circulation has been experimentally investigated based on a natural circulation device with narrow rectangular channels. When heating power reaches a certain range, the Ledinegg flow instability occurs in the system, accompanied by flow oscillation. The stability of the experimental system increases with the increasing of inlet sub-cooling, pressure and size of rectangular channels. Stability boundaries of the system are obtained by the sub-cooling number and the phase change number. It is discovered that there are 4 stages of Ledinegg flow instability in the narrow rectangular channels: condensation, ebullition, choking, and rebalance. Finally, the experience correlation is proposed for the initial power of Ledinegg flow instability in narrow rectangular channels. © 2017 Elsevier Ltd


Chen J.,North China Electrical Power University | Chen J.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | Zhou T.,North China Electrical Power University | Zhou T.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | And 3 more authors.
He Jishu/Nuclear Techniques | Year: 2017

Background: Reactor core of supercritical water-cooled reactor of China (CSR1000) is selected as research object. Purpose: The establishment of thermal-hydraulic calculation model is to calculate coolant outlet flow and the outlet pressure, which is on the condition of changing the core power, flow and temperature distribution, and the size of the core inlet structure. Methods: Taking the SCAC (Steady supercritical water-cooled reactor analysis code) safety analysis code as calculation method. Results: The calculated results show that adjusting moderately the flow distribution of initial inlet fuel assembly will distribute uniformly the flow distribution of respective sub-channel. Inside and outside of the fuel assembly channel outlet pressure drop show an "N" shaped variation. Increasing the inlet core power of internal fuel assembly will reduce the flow distribution within internal fuel assembly. Conclusion: Adjusting moderately the flow distribution of initial inlet core will distribute uniformly the power distribution. © 2017, Science Press. All right reserved.


Hu W.,North China Electrical Power University | Hu W.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | Liu B.,North China Electrical Power University | Liu B.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | And 12 more authors.
Annals of Nuclear Energy | Year: 2015

Minor actinides are the primary contributors to long term radiotoxicity in spent fuel. The majority of commercial reactors in operation in the world are PWRs, so to study the minor actinide transmutation characteristics in the PWRs and ultimately realize the successful minor actinide transmutation in PWRs are crucial problem in the area of the nuclear waste disposal. The key issues associated with the minor actinide transmutation are the appropriate loading patterns when introducing minor actinides to the PWR core. We study two different minor actinide transmutation materials loading patterns on the PWR burnable poison rods, one is to coat a thin layer of minor actinide in the water gap between the zircaloy cladding and the stainless steel which is filled with water, another one is that minor actinides substitute for burnable poison directly within burnable poison rods. Simulation calculation indicates that the two loading patterns can load approximately equivalent to 5-6 PWR annual minor actinide yields without disturbing the PWR keff markedly. The PWR keff can return criticality again by slightly reducing the boric acid concentration in the coolant of PWR or removing some burnable poison rods without coating the minor actinide transmutation materials from PWR core. In other words, loading minor actinide transmutation material to PWR does not consume extra neutron, minor actinide just consumes the neutrons which absorbed by the removed control poisons. Both minor actinide loading patterns are technically feasible; most importantly do not need to modify the configuration of the PWR core and composition of nuclear fuel. Furthermore, the two minor actinide loading patterns completely isolate minor actinide transmutation materials from nuclear fuel, so it also facilitates fuel reprocessing after discharged from PWR core. We believe that loading minor actinide to PWR burnable poison rods for transmutation is an optimal minor actinide loading pattern. © 2014 Elsevier Ltd. All rights reserved.


Li X.-B.,North China Electrical Power University | Li X.-B.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | Zhang M.-C.,North China Electrical Power University | Zhang M.-C.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | And 4 more authors.
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2014

To make the experimental results reflect the actual situation of the prototype, the flow of pressurizer relief steam spraying was analyzed based on dimensional analysis method. The results show that the phenomena similarity between the model and the prototype should meet: Similar geometric structure; equal thermal parameters and same initial conditions, which can greatly simplify other similarity parameters; at the blow-down stage, keeping the steam mass flux density consistent; at the natural convection stage, the Fourier number and the Grashof number should be meet, while assessing relative uncertainty.


Li X.,North China Electrical Power University | Li X.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | Li N.,North China Electrical Power University | Li N.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | And 8 more authors.
Annals of Nuclear Energy | Year: 2016

The passive residual heat removal system (PRHR) plays an important role in AP1000 passive core cooling system during non-LOCA accidents. The temperature of the water in the in-containment refueling water storage tank (IRWST) will increase while the decay heat is removed through the C-tube heat exchanger under accident conditions, resulting in the change of heat transfer mechanism. Therefore, it is essential to study the relevant pool boiling phenomenon in IRWST by means of experiment. To ensure to capture the major ones from a large amount of influence factors associated with pool boiling in IRWST, the phenomena identification and ranking table (PIRT) was analyzed in this paper. The PRHR system was firstly divided into different modules and components based on the PIRT flow chart, and then the general factors associated with local heat transfer were discussed under different pool boiling stages. Finally, the importance levels of different parameters on heat transfer process were evaluated, which can provide some reference for future design of new PRHR system. © 2016 Elsevier Ltd. All rights reserved.


Li X.,North China Electrical Power University | Li X.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | Zhang M.,North China Electrical Power University | Zhang M.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | And 5 more authors.
Annals of Nuclear Energy | Year: 2014

Through the automatic depressurized system of AP1000 reactor, the steam with high temperature and high pressure from the pressurizer sprays into the water tank, and the pressure in the primary coolant system will diminish to protect the reactor. However, as the steam continues to flow into the tank, the water temperature rises rapidly until boiling occurs, which will affect the local heat transfer process. Therefore, it is necessary to understand the corresponding heat transfer mechanism by means of experiment. To ensure that the experimental results with a scale-down model reflect the actual situations of the prototype we analyzed the process of steam jetting from the pipeline into the water tank, and summarized scaling rules based on equation analysis method, including various flow stages. The results show that the phenomena-based similarity between the model and the prototype should meet: (1) geometrically similar model and prototype; (2) equal thermal parameters and identical initial conditions, which can greatly simplify other similarity parameters; (3) at the blowdown stage, keep the steam mass flux and the nozzle diameter consistent; (4) at the natural convection stage with single phase fluid, the equality in terms of Prandtl number and the Grashof number should be met first, while assessing the relative uncertainty. © 2014 Elsevier Ltd. All rights reserved.


Wu G.,North China Electrical Power University | Wu G.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | Lu D.,North China Electrical Power University | Lu D.,Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy | And 8 more authors.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2016

Based on the design of AP1000 power plant, a fully scaled experimental mock-up was built to simulate the high-temperature and high-pressure steam spraying, steam condensation under depressurization condition through Automatic Depressurized System (ADS). The experiment recorded the flow characteristics and 3D temperature and velocity distribution around sprayer in IRWST by dot matrix of thermocouples and Particle Image Velocimetry Particle Image Velocimetry (PIV). By studying the thermal stratification and natural circulation in the IRWST under depressurization condition when undercooling water is large, an optimization scheme was proposed to improve the efficiency of cooling water in IRWST. © 2016, Yuan Zi Neng Chuban She. All right reserved.

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