Material Selection Methodology Used in Czech NPP

2009 ◽  
Author(s):  
Karel Matocha
Keyword(s):  
Physical Properties ◽  
Material Properties ◽  
Nuclear Power ◽  
Power Plants ◽  
Mechanical Characteristics ◽  
Material Selection ◽  
Technical Documentation ◽  
Parent Materials ◽  
Materials Used ◽  
Selection Methodology

The paper describes the structure of the Standard Technical Documentation A.M.E Section II “Material Properties for Equipments and Pipings of WWER Nuclear Power Plants”. It provides instructions for selection and qualification of parent materials used for manufacture, repair, reconstruction or replacement of selected equipments of WWER NPP and specifies requirements for mechanical characteristics and physical properties.

Material Selection Methodology Used in Czech NPP

2011 ◽  
Vol 133 (1) ◽  
Author(s):  
Karel Matocha
Keyword(s):  
Czech Republic ◽  
Material Properties ◽  
Nuclear Power ◽  
Power Plants ◽  
Mechanical Characteristics ◽  
Material Selection ◽  
Technical Documentation ◽  
Parent Materials ◽  
Materials Used ◽  
Selection Methodology

This paper describes the structure of the Standard Technical Documentation of the Association of Mechanical Engineers of Czech Republic, Sec. II, “Material Properties for Equipments and Pipings of Water moderated, Water Cooled Energy Reactor (WWER) Nuclear Power Plants (NPPs).” It provides instructions for selection and qualification of parent materials used for manufacture, repair, reconstruction, or replacement of selected equipments of WWER NPP, and specifies requirements for mechanical characteristics and physical properties.

Research Progress on Radiation Shielding Concrete

2012 ◽  
Vol 253-255 ◽  
pp. 303-307 ◽  
Author(s):  
Jing Yang ◽  
Zhen Fu Chen ◽  
Yuan Chu Gan ◽  
Qiu Wang Tao
Keyword(s):  
Nuclear Waste ◽  
Material Properties ◽  
Nuclear Power ◽  
Power Plants ◽  
Radiation Shielding ◽  
Nuclear Industry ◽  
Research Progress ◽  
Concrete Durability ◽  
Technology Research ◽  
Shielding Material

Radiation shielding concrete is widely used in nuclear power plants, accelerators, hospitals, etc. With the development of nuclear industry technology, research on radiation shielding material properties is of great importance. Research on properties of radiation shielding concrete with different aggregates or admixtures and the effect of high temperature on the performance of shielding concrete are introduced. Along with the nuclear waste increase, shielding concrete durability and nuclear waste disposal are getting paramount.

Research on the Micro-Mechanical State at Tip of Environmentally Assisted Cracking Based on Latin Hypercube Sampling Method

2019 ◽  
Vol 795 ◽  
pp. 74-78
Author(s):  
Kuan Zhao ◽  
He Xue ◽  
Ling Yan Zhao
Keyword(s):  
Oxide Film ◽  
Material Properties ◽  
Nuclear Power ◽  
Power Plants ◽  
Sampling Method ◽  
Latin Hypercube Sampling ◽  
Primary Circuit ◽  
Mechanical State ◽  
Latin Hypercube ◽  
Environmentally Assisted Cracking

Environmentally assisted cracking (EAC) of nickel-based alloys is one of the most significant potential safety hazards in the primary circuit of nuclear power plants. To understand the influence of randomness on micro-mechanical state at tip of EAC, Latin hypercube sampling method is applied to analyze the uncertainty of stress-strain in the oxide film at the EAC tip considering the uncertainties of load and material properties of base metal and oxide film. Meanwhile, to improve the efficiency of numerical analysis, MATLAB is employed in the secondary development for ABAQUS. With the help of finite element numerical simulation and Latin hypercube sampling method, the uncertainty of mechanical properties at tip of EAC in one-inch compact tension specimen is simulated and analyzed in this study. The results show that the randomness of material properties and load markedly affect the uncertainty of micro-mechanical state. Among the variables, The randomness of load has the greatest influence on uncertainty of strain, and Poisson`s ratio of oxide film is the smallest effect.

Influence of the composition of α-titanium alloys on thermal conductivity

2021 ◽  
pp. 79-86
Author(s):  
I. A. Schastlivaya ◽  
V. P. Leonov ◽  
I. V. Tretyakov ◽  
A. Yu. Askinazi
Keyword(s):  
Thermal Conductivity ◽  
Titanium Alloys ◽  
Nuclear Power ◽  
Power Plants ◽  
Operating Temperature ◽  
Unique Combination ◽  
Specific Strength ◽  
High Specific Strength ◽  
Heat Exchange Equipment ◽  
Materials Used

Among titanium alloys, modern α- and pseudo-α-alloys occupy a special place due to the unique combination of their mechanical properties, corrosion resistance, low density and high specific strength, which determines their effectiveness in various industries. Analysis of structural materials used for heat exchange equipment of nuclear power plants showed that the increase in the efficiency and compactness of tube systems made of a-titanium alloys is constrained by their thermal conductivity characteristic, which does not exceed 89 W/(m·K) at a temperature of 20°C. An exception is the VT1-0 grade alloy, the scope of which is limited to a maximum operating temperature of no more than 250°C. The paper considers the results of studies of a new titanium alloy of the Ti-Zr-Al-O composition with increased thermal conductivity for pipe systems of power equipment. 

Application of Metallographic Methods for Thermal Ageing Evaluation on Samples from Primary Piping of NPP

2017 ◽  
Vol 891 ◽  
pp. 60-66
Author(s):  
Jana Petzová ◽  
Martin Březina ◽  
Miloš Baľák ◽  
Mária Dománková ◽  
Ľudovít Kupča
Keyword(s):  
Material Properties ◽  
Nuclear Power ◽  
Power Plants ◽  
Operating Temperature ◽  
Thermal Ageing ◽  
Primary Circuit ◽  
Degradation Mechanisms ◽  
Reliable Operation ◽  
Term Operation

During a long-term operation of nuclear power plants (NPP), the changes of structural material properties occur. To ensure the safe and reliable operation, it is necessary to monitor and evaluate these changes mainly on components from primary circuit of NPPs. One of the dominant ageing mechanisms of NPP components besides the radiation embrittlement and the fatigue loads is the thermal ageing. The thermal ageing is the temperature, material and time dependent degradation mechanisms due to long-term exposure at the operating temperature of 570 K.This paper describes the project for thermal ageing monitoring at primary piping in NPP Bohunice Unit 3. There are summarized the results obtained from evaluation of original primary piping material.

scholarly journals A REVIEW ON USAGE OF NANO-PARTICLES IN NUCLEAR POWER PLANTS

2017 ◽  
Vol 5 (2) ◽  
pp. 233-236
Author(s):  
Din Bandhu ◽  
Ritesh Kumar
Keyword(s):  
Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Review Paper ◽  
Nano Particles ◽  
Construction Experience ◽  
And Performance ◽  
Materials Used ◽  
Effects Of Radiation

Nuclear power plants are big in construction and possess complex facilities. These plants usually operate at very large temperatures and the materials used in their construction experience considerably higher levels of radiation. It is therefore very important to understand the effects of radiation on these materials. Radiation is responsible for defects which affects the strength and performance of the materials. In this review paper, we have suggested one idea for constructing an efficient nuclear power plant by using nano-particles. This paper also details about nano-particles in an elaborated way and a few of them can be used for constructing nuclear power plants (NPP).

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