scholarly journals Development of Red Mud Paver Blocks Prepared From Nuclear Power Plant

2020 ◽  
Vol 13 (1) ◽  
pp. 54-68
Author(s):  
A Jayaraman ◽  
V Senthilkumar
Keyword(s):  
Compressive Strength ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Portland Cement ◽  
Red Mud ◽  
Nuclear Power ◽  
Waste Material ◽  
Bayer Process ◽  
Test Results ◽  
The World

Red mud is a waste material generated by the Bayer Process widely used to produce alumina from bauxite throughout the world. The aim of the project is to say the possibility of replacing the Portland cement by red mud. Because it negatively affects the environment. To solve this problem, Portland cement was replaced up to 20% red mud by weight of cement. And evaluating its compressive strength of red mud paver tiles. This project examines the effects of red mud on the properties of hardened paver tile. The test results show that how its compressive strength becomes equivalent to normal paver tile without red mud content, it is concluded that optimum percentage of the replacement of cement by weight is found to be. By this percentage replacement we can have 15%strength is equal to the strength of normal paver tile.

Strength and Toughness of Steel Fiber Reinforced Heavy Concrete

2012 ◽  
Vol 512-515 ◽  
pp. 2908-2913 ◽  
Author(s):  
Yu Cheng Kan ◽  
Hsuan Chih Yang ◽  
Kuang Chih Pei
Keyword(s):  
Experimental Study ◽  
Compressive Strength ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Iron Ore ◽  
Steel Fiber ◽  
Test Results ◽  
Spent Fuel ◽  
Normal Concrete

This paper presents an experimental study dealing with the toughness of heavy concrete based on the ASTM C1018. Mixtures including 0%, 0.5%, 1.0% and 1.5% of steel fiber content by volume are designated, which are developed based on a mixture used in Kuosheng nuclear power plant in Taiwan. Metallic aggregates of iron shots and iron ore take 48.8% by volume in that mixture. Test results reveal that the compressive strength and rupture modulus of heavy concrete turn out higher than those of normal concrete. In addition, flexural toughness of heavy concrete grow with the steel fiber fraction, which is valid and appropriate for construction of shielding structure and spent fuel cask.

Electrochemical decontamination of irradiated nuclear graphite from corrosion and fission products using molten salt

2021 ◽  
Author(s):  
Tatiana Grebennikova ◽  
Abbie N Jones ◽  
Clint Alan Sharrad
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Waste Management ◽  
Molten Salt ◽  
Nuclear Power ◽  
Fission Products ◽  
Nuclear Graphite ◽  
Irradiated Graphite ◽  
The World ◽  
The Uk

Irradiated graphite waste management is one of the major challenges of nuclear power-plant decommissioning throughout the world and significantly in the UK, France and Russia where over 85 reactors employed...

Shrinkage Cracking Resistance Property of Self-Compacting Concrete

2011 ◽  
Vol 250-253 ◽  
pp. 383-387
Author(s):  
Xian Yu Jin ◽  
Chuan Qing Fu ◽  
Nan Guo Jin ◽  
Fan Ge ◽  
Yi Bing Zhao
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Design Theory ◽  
Test Results ◽  
Self Compacting Concrete ◽  
Cracking Resistance ◽  
Shrinkage Cracking ◽  
Resistance Property ◽  
Mix Proportion

Based on the project requirement of a nuclear power plant, using the method of free shrinkage test and ring cracking test, shrinkage cracking resistance property of grade C35 and C50 self-compacting concrete (SCC) with the optimized mix proportion was studied. The test results between SCC and ordinary vibrated concrete afforded by nuclear power plant project with the same grade were compared. The results indicated that the shrinkage cracking resistance property of SCC is prior to the ordinary vibrated concrete with the same strength grade. This kind of SCC can satisfy the nuclear power plant project, also the test results can be a reference of SCC design theory.

Consideration of Relationship Between Decommissioning With Digital-Twin and Knowledge Management

2020 ◽  
Author(s):  
Yasuyoshi Taruta ◽  
Satoshi Yanagihara ◽  
Takashi Hashimoto ◽  
Shigeto Kobayashi ◽  
Yukihiro Iguchi ◽  
...  
Keyword(s):  
Knowledge Management ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Digital Technology ◽  
Nuclear Power ◽  
Next Generation ◽  
Digital Twin ◽  
Advanced Technologies ◽  
The World

Abstract Decommissioning of Nuclear Power Plant is a long-term project during which generations are expected to change. Therefore, it is necessary to appropriately transfer knowledge, technology and skills to the next generation. In recent years, in the world of decommissioning, attempts have been made to apply advanced technologies such as utilization of knowledge management and digital technology. This study describes adaptation in decommissioning from viewpoint of utilizing IT technology called digital twin and aspect of knowledge management.

Life Prediction Model for Nuclear Power Plant Intake Structure Exposed to Chloride Environment Based on Similarity Principle

2020 ◽  
Author(s):  
Sen Chen ◽  
Zhen Wang ◽  
Jiangtao Zhang ◽  
Dahua Cai ◽  
Jiyun Zhou
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Salt Spray ◽  
Chloride Ion ◽  
Ion Concentration ◽  
Test Results ◽  
Ion Diffusion ◽  
Similarity Principle ◽  
Intake Structure

Abstract Three environmental simulation experiments for accelerating the chloride ingress were designed based on the similarity principle and the actual Nuclear Power Plant (NPP) intake structure service environment parameters including alternate drying-wetting condition, immersion condition and salt spray condition. Different experiment conditions were designed for each three-simulation experiment condition based on the similarity principle. The temperature, chloride ion concentration and dry-wet cycle time ratio were selected parameters for alternation wetting-drying experiments. The temperature and chloride ion concentration were selected parameters for the salt spray experiment and immersion experiment. The distribution of chloride ion concentration along the depth of the concrete samples were measured every 30 days. The testing results showed that chloride ion diffusion depth is maximum under the dry-wet cycle test, chloride ion diffusion depth is minimum under salt spray test. The curves of the chloride ion concentration along depth increased firstly and then decreased, which is consistent with the two-dimension diffusion law. Finally, a life prediction model that can be used to predict the concrete structure of the existing coastal nuclear power plant was developed based on the test results and field test results.

Research on Project Management of DCS Development for First AP1000 Unit

2013 ◽  
Author(s):  
Shihong Ma
Keyword(s):  
Control System ◽  
Project Management ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety Control ◽  
The World

Sanmen Nuclear Power Plant is constructing the first AP1000 unit in the world, and DCS system is adopted as the non-safety control system. This paper reviews the experience of Sanmen project, and analyzes the necessity of nuclear power plant Owner’s management for developing the DCS system, as well as how to manage the development effectively.

Relation between Uniaxial Compressive Strength and Physical Parameters of Rock in a Nuclear Power Plant

2017 ◽  
Vol 865 ◽  
pp. 373-382
Author(s):  
Jing Sen Liu ◽  
Hai Bo Li ◽  
Bo Liu ◽  
Guo Kai Zhang ◽  
Wei Zhou
Keyword(s):  
Compressive Strength ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Uniaxial Compressive Strength ◽  
Nuclear Power ◽  
Empirical Equation ◽  
P Wave ◽  
Physical Parameters ◽  
Mechanical Parameters ◽  
P Wave Velocity

In order to improve the accuracy of the selection on rock mechanical parameters, the relation between uniaxial compressive strength (UCS) and physical mechanical parameters should be investigated. A great number of physical and mechanical tests on rock in the first-stage of Guangxi Fangchenggang Nuclear Power Plant (GFNPP) are conducted. Mineral identification tests of rocks are conducted, and rocks are divided into two groups (A and B) according to the result of the test. The correlation coefficient between rock UCS and rock physical parameters (porosity, density and P-wave velocity) are calculated by using Pearson’s analytical method. The result shows that the relationship between physical parameters and mechanical parameters of rock is influenced significantly by content of quartz. Regression analysis method is used to explore the relation between UCS and porosity, density, P-wave velocity of rock; combined with the dimensional analysis, the relation between UCS and rock physical parameters was established. Based on normality test and randomness test, the best fitting equation is determined as the empirical equation of UCS. The empirical equation was used to forecast the UCS of rock in the second-stage of GFNPP, comparative results show that the forecasting value and the experimental value are in good agreement.

Seismic Test Result of Motor-Operated Butterfly Valve Actuators for Nuclear Power Plant

2018 ◽  
Author(s):  
Nobuo Kojima ◽  
Yoshitaka Tsutsumi ◽  
Kazuyoshi Yonekura ◽  
Koji Nishino ◽  
Yukio Watanabe ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Earthquake Resistance ◽  
Test Results ◽  
Butterfly Valve ◽  
Resistance Evaluation ◽  
Vibration Tests ◽  
Seismic Tests ◽  
Test Result

Seismic tests were carried out to confirm the operability limit acceleration for a standard motor-operated butterfly valve actuator in three excitation directions. Based on the results, seismic brackets that can operate valves even in three directions at 20 × 9.8 m/s2 or more were designed in three representative models. For the model subjected to the seismic test, we mounted the designed seismic bracket and confirmed the operability of the butterfly valve actuator by carrying out vibration tests in three directions at 20 × 9.8 m/s2. We used these results and previously reported motor-operated valve actuator seismic test results to creat a revision (draft) of the earthquake resistance evaluation methods.

scholarly journals Analysis of Heat Transfer in The VVER-1200 Reactor’s Heat Channel

2017 ◽  
Vol 33 (3) ◽  
Author(s):  
Thin Dinh Van ◽  
Loat Van Bui ◽  
Hong Thi Bui
Keyword(s):  
Heat Transfer ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
High Reliability ◽  
Modern Method ◽  
Safe Operation ◽  
The World ◽  
The Government ◽  
First Time

In early 2015, the Government of Vietname has decided to choose VVER-1200 Russian-made technology for building at the Nuclear Power Plant in Ninh Thuan 1, this is the advanced reactor generation III + and the only one has been completed for the first time in the world in August 2016. Vietnam is facing a major challenge, which is how to ensure the acquired technology transfer process, then the safe operation of thisunit. This article analyzes some of the heat changes occur in reactor when there are changes of the heatflux. This is an issue directly related to the workof predictingincidents and give ways to fix the problem when the plant is in conditions such as  startup, normal and abnormaloperations. For analysis, the authors used CFD methods, this is a very modern method and have high reliability. The results received have fit well when compared with the safety analysis report of Rosatom published.

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