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.

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.

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.

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.

Analysis of Reasons for Non-Conformance of the Movable Latch Lock Plunger Releasing Current of Control Rod Drive Mechanism and Improvement Measures

2017 ◽  
Author(s):  
Yinhui Lan ◽  
Cuizhu He ◽  
Yuangang Duan ◽  
Feihua Liu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Performance Test ◽  
Cold Test ◽  
Test Results ◽  
Suction Force ◽  
Control Rod ◽  
Drive Mechanism ◽  
Hot Test

As one of the most important equipment for reactivity control, Control Rod Drive Mechanism (CRDM), which is widely used in pressurized water reactor (PWR) nuclear power plant, has a series of important security functions. As an important component of the claw part in CRDM, the nonmagnetic shim materials have big influence on the movable latch lock plunger releasing current of CRDM. When cutting off the coil power, the nonmagnetic shim materials can block the magnetic circuit between the pole and latch lock plunger effectively and reduce the remanence suction force between magnetic pole and latch lock plunger, which can promote a quick latch lock plunger’s action and finish the step-jump and rod-release. In this paper, we introduce the background of non-conformance of the movable latch lock plunger releasing current of CRDM of PWR plant simply, and then we analyze the reasons of the non-conformance in detail, including a comprehensive analysis of various factors and a series of retest conclusions. Through specific analysis, the important role of nonmagnetic shims in CRDM and its big influence on movable latch lock plunger releasing current are proved. Based on research and test results, we show our optimized measures on the movable latch lock plunger releasing current in detail, from the perspective of technical specification for raw materials and improved processing technology during production. At last, one latch unit which occurred the movable latch lock plunger releasing current non-conformance and experienced a 1.7 million steps performance test is used in the following performance verification test. Being installed in this latch mechanism, our nonmagnetic shims finished an integral series of cold test, hot test and cold test after hot test. All of the test results meet our design requirements and all of the releasing current under cold condition is better than the results of 1.7 million steps performance test. Especially, the independently developed nonmagnetic shims improved the movable latch lock plunger releasing current significantly. In addition, other current results of hot test are equal to that of 1.7 million steps performance test. In conclusion, these optimized measures may not only provide data for solving the problem completely, but also provide reference for the manufacture of nonmagnetic shim materials in the future nuclear power plant.

Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model

2018 ◽  
Vol 4 (3) ◽  
Author(s):  
Xiong Wenbin ◽  
Cao Jian ◽  
Huang Chaoyun ◽  
Bie Yewang ◽  
Wang Yanqi ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Reactor Core ◽  
Nuclear Regulatory Commission ◽  
Physical Parameters ◽  
Test Results ◽  
Design Values ◽  
Regulatory Commission ◽  
Ap1000 Reactor

This study investigates the reactor core physical properties of the AP1000®, which applies the MCNP4a program to model the AP1000 reactor core with the parameters and data from the design control document (DCD, Rev. 19) of the AP1000 Nuclear Power Plant, which has been submitted to the nuclear regulatory commission (NRC). The model is applied to calculate and verify the physical parameters of AP1000 core design. The results match well with the design values in the DCD of the AP1000 nuclear power plant. The model will be modified according to the actual reactor core arrangement, such as AP1000 reactors at China's Sanmen and Haiyang sites, and then compared with the commissioning test results in the future.

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.

Research on the Computerized Symptom-Oriented Procedures of Nuclear Power Plants

2008 ◽  
Author(s):  
Fei Liu ◽  
Zhijian Zhang ◽  
Minjun Peng
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Interface Design ◽  
Nuclear Power ◽  
Power Plants ◽  
Test Results ◽  
Pressurized Water ◽  
Water Reactors ◽  
Steam Generator Tubes ◽  
Emergency Operating

New methods of information presentation and interface design are changing the working conditions in the modern Nuclear Power Plant (NPP) control room. Symptom-oriented EOPs (SOPs) with their structures and practical application are described. The Computerized Symptom-oriented Operating Procedures (CSOP) is researched, which can help the operator analyze all the symptom signals of steam generator tubes rupture (SGTR) and provide the computerized procedures corresponding to the symptom signals. This paper analyzes the accident of SGTR; the accident management of SGTR is important in reactor safety because SGTR is one of the relatively high-frequency events in pressurized water reactors PWRs. The symptom signals of SGTR and the possible accidents corresponding to the symptom signals are analyzed. The homologous measures of symptoms are summarized. The disposal of SGTR adopts the method of based on symptoms. The programs are developed by VxWorks that is a real-time operating system. The debugging of programs is processed on simulator. The test results indicated that the programs can provide operating procedures according to the symptoms of accidents. After adopting the Computerized Emergency Operating Procedures, the labor intensity and mental burden of operators are lightened. Computerized Emergency Operating Procedures can enhance the reliability, safety and efficiency of Nuclear Power Plant.

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