THE IMPACT OF RUSSIAN-CHINESE INTER-REGIONAL AND CROSS-BORDER COOPERATION ON ENTREPRENEURSHIP DURING THE GLOBAL ECONOMIC CRISIS by Xin Ran

“…Within the framework of regular meetings between the two governments signed a series of agreements and contracts in the oil and gas industry, the coal industry, as well as in the nuclear power industry and in the field of high-speed rail train and automobile, etc. …”
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Thermomechanical Analysis of the Effects of Water Distribution on Cracks during Vertical Continuous Casting under Soft Reduction Conditions by Yu Yao, Bo Wang, Shanshan Liu, Liping Zhong, Shiyi Shen, Zheng Chen, Jieyu Zhang

“…This study focuses on the problem of cracks in nuclear power stainless steel produced by vertical continuous casting under soft reduction conditions. …”
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Simulation Results of a Thermal Power Dispatch System from a Generic Pressurized Water Reactor in Normal and Abnormal Operating Conditions by Stephen Hancock, Dylan Jurski, Thomas A. Ulrich, Roger Lew, Jisuk Kim, Olugbenga Gideon

“…These results indicate that an industrial hydrogen production plant could be coupled thermally to a nuclear power plant with limited effects on the existing system operation and safety.…”
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Scientometric Analysis of Human Error Research and Human Reliability in Industries (1980-2022) by Hamed Yarmohammadi, Mehdi Jahangiri, Moslem Ali Mohammadloo, Mojtaba Kamalinia

“…VOSviewer and Bibliometrix, an R package, were used to perform the scientometric analysis of these articles.Results: Industrial human error research is generally related to marine safety and accidents, the aviation industry, nuclear power plants, oil and petrochemical industries, occupational accident analysis, occupational fatigue, ergonomic issues, safety analysis of process systems, and the construction industry. …”
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Research on Application of Dredging Technology for Steel Pipe Pile Under Complex Sea Conditions in Deep Sea by Jianjun CHEN

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Effect of the Size and Position of a Damping Ditch on the Reduction of the Blasting Vibration by Baofu Duan, Shizhan Shen, Guoshan Ta, Kebin Sun, Wei Hou, Li Gu

“…In order to explore the effect of damping ditches of different sizes and positions, we investigated field blasting in the A3 area of the second phase of the Lufeng Nuclear Power Plant project. The simulation software ANSYS/LS-DYNA was used to simulate the vibration propagation of damping ditches with different depths, widths, and positions. …”
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Parametric Optimization for Automatic Control System of 300 MW Power Units at a Constant Steam Pressure Upstream of the Turbine by G. T. Kulakov, A. T. Kulakov, K. I. Artsiomenka

“…The total capacity of the Belarusian Nuclear Power Plant will amount to 2400 MW. In addition, modern requirements for the regulation of the frequency and flows of active electric power in the power system have been tightened: the time to reach the half value of the required power alteration should be 10 seconds within the normal and emergency reserves; the time to reach the full value of the required power alteration should be 30 seconds within the range of the normal reserve and 2 minutes – within the range of the emergency reserve. …”
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Study on Seismic Coefficient Calculation Method of Slope Seismic Stability Analysis by Pai Lifang, Wu Honggang, Yang Tao, Zhong Feifei

“…Moreover, the results obtained from the method of nuclear power plant specification were relatively small compared to other specification methods. …”
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Steam Generator Maintenance Robot Design and Obstacle Avoidance Path Planning by Fengwei Yuan, Gengzhen Ren, Qian Deng, Xiangjiang Wang

“…To solve the issue of inconvenient and dangerous manual operation during the installation and removal of the main pipe plugging plate in the steam generator in nuclear power plants, a ten-degree-of-freedom plugging robot was designed in the present study that includes a collaborative robotic arm coupled with a servo electric cylinder. …”
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Experimental and CFD Investigation on Flow Behaviors of a NPP Pump under Natural Circulation Condition by Weitong Li, Lei Yu, Jianli Hao, Mingrui Li

“…Passive safety system is the core feature of advanced nuclear power plant (NPP). It is a research hotspot to fulfill the function of passive safety system by improving the NPP natural circulation capacity. …”
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Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor by Mingjun Wang, Qiaolin Zuo, Hao Yu, Wenxi Tian, G. H. Su, Suizheng Qiu

“…In this paper, the multiscale thermal hydraulic analysis was performed for Chashma Nuclear Power Plant (NPP) under the inadvertent SIS operation scenario. …”
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Multivariate polynomial fit: Decay heat removal system and pectin degrading Fe3O4‐SiO2 nanobiocatalyst activity by Boopathi Muthusamy, Sujatha Ramalingam, Senthil Kumar Chandran, Sathish Kumar Kannaiyan

“…Here, the three parameters namely: pH value, pectinase loading and temperature as independent variables are optimized for the maximal of anobiocatalyst activity as a dependent variable. (2) For a passive system reliability estimation of decay heat removal (DHR) of a nuclear power plant. The success criteria of the system depend on three types temperature that do not exceed their respective design safety limits and are considered as dependent variables and 14 significant parameters were used as independent variables. …”
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TO THE SUBJECT OF DEVELOPMENT OF POWER SUPPLY PROCESS FOR INDUSTRIAL HEAT TECHNOLOGIES AND HEAT SUPPLY SYSTEMS IN BELARUS by B. M. Khrоustalev, V. N. Romaniuk, V. A. Sednin, A. A. Bobich, D. B. Muslina, T. V. Bubyr

“…It must be emphasized, that such an expansion of energy-saving framework not only reduce the primary energy consumption by heat generating sources, but also significantly improves the conditions of the Belarusian electrical grid operation under the conditions of nuclear power plant commissioning. The existing technical framework, that ensured the proposed changes, is also taking into account.…”
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International Course to Support Nuclear Licensing by User Training in the Areas of Scaling, Uncertainty, and 3D Thermal-Hydraulics/Neutron-Kinetics Coupled Codes: 3D S.UN.COP Semi... by Alessandro Petruzzi, Francesco D'Auria, Tomislav Bajs, Francesc Reventos, Yassin Hassan

“…Thermal-hydraulic system computer codes are extensively used worldwide for analysis of nuclear facilities by utilities, regulatory bodies, nuclear power plant designers, vendors, and research organizations. …”
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Numerical Study of Bubble Rising and Coalescence Characteristics under Flow Pulsation Based on Particle Method by Ronghua Chen, Minghao Zhang, Kailun Guo, Dawei Zhao, Wenxi Tian, Guanghui Su, Suizheng Qiu

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On the One-Dimensional Modeling of Vertical Upward Bubbly Flow by C. Peña-Monferrer, C. Gómez-Zarzuela, S. Chiva, R. Miró, G. Verdú, J. L. Muñoz-Cobo

“…The one-dimensional two-fluid model approach has been traditionally used in thermal-hydraulics codes for the analysis of transients and accidents in water–cooled nuclear power plants. This paper investigates the performance of RELAP5/MOD3 predicting vertical upward bubbly flow at low velocity conditions. …”
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A review on the anomalous exothermic behavior of bubbles in aluminum induced by electron irradiation by Qicong Chen, Yupeng Yin, Wentuo Han, Xiaoou Yi, Pingping Liu, Qian Zhan, Somei Ohnuki, Farong Wan

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Effect of environmental factors on the corrosion behavior of CoCrNi and CoCrFeMnNi alloys in 3.5 wt% NaCl solution by Ruizhen Xie, Yifan Wei, Kunjie Luo, Naiming Lin, Yuan Yu, Peng Cheng, Qunfeng Zeng

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Time-dependent model for in-situ concrete carbonation depth under combined effects of temperature and relative humidity by Ting Du, Yongjia Cai, Yipu Guo, Jinghao Chen, Sen Chen, Mofang Yuan, Fulin Qu

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Standalone Containment Analysis of Four Phébus Tests with the ASTEC and the MELCOR Codes by Bruno Gonfiotti, Sandro Paci

“…After the severe accident (SA) occurred at the Three-Miles Island Nuclear Power Plant (NPP), important efforts on the investigation of the different phenomena during this kind of accidents have been started. …”
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