Microstructural Changes of Mechanical Properties of 08Cr18Ni10Ti Austenitic Steel under Neutron Irradiation

2017 ◽  
Vol 743 ◽  
pp. 37-40
Author(s):  
Daniyar Esimgaliuly Ashimov ◽  
Erbolat Taitoleuovich Koyanbayev ◽  
Sherzod Rustambekovich Kurbanbekov ◽  
Alexander Andreevich Sitnikov ◽  
Maznyn Kanapinovich Skakov
Keyword(s):  
Mechanical Properties ◽  
Radiation Dose ◽  
Austenitic Steel ◽  
Neutron Irradiation ◽  
Research Reactor ◽  
Structural Materials ◽  
Microstructural Changes ◽  
Material Analysis ◽  
Hardness Values

This paper reports neutron irradiation induced effects on 08Cr18Ni10Ti austenitic steel, which is one of the structural materials of the IVG.1M research reactor. Chosen samples were stored in the beryllium displacer at two different elevation heights and the radiation dose with fast fluence of 0.4·1019 n/cm2 and 4.3·1019 n/cm2. Thorough material analysis reports changes in hardness values, plasticity and microstructure

scholarly journals Physical Ageing of The Research Reactor Core Structural Materials Due To Neutron Irradiation Exposure: A Review

2017 ◽  
Vol 18 (2) ◽  
pp. 93
Author(s):  
Julwan Hendry Purba
Keyword(s):  
Neutron Irradiation ◽  
Nuclear Reactor ◽  
Research Reactor ◽  
Reactor Core ◽  
Structural Materials ◽  
Industrial Applications ◽  
Physical Ageing ◽  
Functional Capabilities ◽  
Wide Range ◽  
The Stability

A research reactor (RR) is a nuclear reactor that has function to generate and utilize neutron flux and radiation ionization for research purposes and industrial applications. More than 60% of current operating RRs have been operated for 30 years or more. As the time passes, the functional capabilities of structures, systems and components (SSCs) of those RRs deteriorate by physical ageing, which can be caused by neutron irradiation exposure such as irradiation induced dislocation and microstructural changes. To extend the lifetime and/or to avoid unplanned outages, ageing on the safety related SSCs of RRs need to be properly managed. An ageing management is a strategy to engineer, operate, maintenance, and control SSC degradation within acceptablelimits. The purpose of this study is to review physical ageing of the core structural materials of the RRs caused by neutron irradiation exposure. In order to achieve this objective, a wide range of literatures are reviewed. Comprehensive discussions on irradiation behaviors are limited only on reactor vessel and core support structure materials made from zirconium and beryllium as well as their alloys, which are widely used in RRs. It is found that the stability of the mechanical properties of zirconium and beryllium as well as their alloys was mostly affected by the neutron fluences and temperatures.

scholarly journals APPLICATION OF INTERVAL ANALYSIS FOR IMPROVING RELIABILITY OF ESTIMATION OF HARDNESS VALUE SPREAD FOR NUCLEAR STRUCTURAL MATERIALS

2020 ◽  
pp. 206-210
Author(s):  
A.V. Yefimov ◽  
Т.V. Potanina
Keyword(s):  
Experimental Data ◽  
Mechanical Properties ◽  
Measurement Error ◽  
Numerical Methods ◽  
Interval Analysis ◽  
Structural Materials ◽  
Reliable Information ◽  
Nuclear Materials ◽  
Mass Content ◽  
Hardness Values

The applications of the interval and standard probabilistic approaches for verifying the reliability of the results of an experiment studying the mechanical properties of nuclear materials are compared. The presence of “outliers” in a sample of hardness values for hafnium ingots is studied with for fixed oxygen mass content. The situation of measurement error limitation without reliable information about its distribution is considered. The correctness of the application of numerical methods of interval analysis for processing experimental data under conditions of uncertainty and noisy experimental data is shown.

Structure, Phase Composition, and Mechanical Properties of a Boron-Containing High-Nitrogen Austenitic Steel Made by Induction Melting

2020 ◽  
Vol 2020 (12) ◽  
pp. 1439-1445
Author(s):  
I. O. Bannykh ◽  
O. A. Bannykh ◽  
L. G. Rigina ◽  
E. N. Blinova ◽  
K. Yu. Demin ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Phase Composition ◽  
Austenitic Steel ◽  
Induction Melting ◽  
High Nitrogen ◽  
Structure Phase

Micro-Hardness and Morphology of LDPE Influenced by Beta Radiation

2014 ◽  
Vol 606 ◽  
pp. 253-256 ◽  
Author(s):  
Martin Ovsik ◽  
Petr Kratky ◽  
David Manas ◽  
Miroslav Manas ◽  
Michal Stanek ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Hardness Test ◽  
Polymer Materials ◽  
Beta Radiation ◽  
Micro Hardness ◽  
X Ray Diffraction ◽  
Depth Sensing ◽  
Surface Layers ◽  
Hardness Values ◽  
Different Doses

This article deals with the influence of different doses of Beta radiation to the structure and mico-mechanical properties of Low-density polyethylene (LDPE). Hard surface layers of polymer materials, especially LDPE, can be formed by radiation cross-linking by β radiation with doses of 33, 66 and 99 kGy. Material properties created by β radiation are measured by micro-hardness test using the DSI method (Depth Sensing Indentation). Individual radiation doses caused structural and micro-mechanical changes which have a significant effect on the final properties of the LDPE tested. The highest values of micro-mechanical properties were reached at radiation dose of 66 and 99 kGy, when the micro-hardness values increased by about 21%. The changes were examined and confirmed by X-ray diffraction.

The Effect of Aging Heat Treatment on the Microstructure and Mechanical Properties of 10Cr20Ni25Mo1.5NbN Austenitic Steel

2016 ◽  
Vol 35 (1) ◽  
pp. 1-7 ◽  
Author(s):  
Zhiyuan Liang ◽  
Wanhua Sha ◽  
Qinxin Zhao ◽  
Chongbin Wang ◽  
Jianyong Wang ◽  
...  
Keyword(s):  
Electron Microscopy ◽  
Mechanical Properties ◽  
Heat Treatment ◽  
Austenitic Steel ◽  
Treatment Time ◽  
Aging Treatment ◽  
Secondary Phases ◽  
Aging Heat Treatment ◽  
Microstructure And Mechanical Properties ◽  
The Impact

AbstractThe effect of aging heat treatment on the microstructure and mechanical properties of 10Cr20Ni25Mo1.5NbN austenitic steel was investigated in this article. The microstructure was characterized by scanning electron microscopy, energy dispersive spectrometry and transmission electron microscopy. Results show that the microstructure of 10Cr20Ni25Mo1.5NbN austenitic is composed of austenite. This steel was strengthened by precipitates of secondary phases that were mainly M23C6 carbides and NbCrN nitrides. As aging treatment time increased, the tensile strength first rose (0–3,000 h) and then fell (3,000–5,000 h) due to the decrease of high density of dislocations. The impact absorbed energy decreased sharply, causing the sulfides to precipitate at the grain boundary. Therefore, the content of sulfur should be strictly controlled in the steelmaking process.

scholarly journals Experimental Evaluation of Mechanical Properties of Friction Welded Dissimilar Steels under Varying Axial Pressures

2016 ◽  
Vol 66 (1) ◽  
pp. 27-36 ◽  
Author(s):  
Amit Handa ◽  
Vikas Chawla
Keyword(s):  
Mechanical Properties ◽  
Tensile Strength ◽  
Impact Strength ◽  
Failure Analysis ◽  
Friction Welding ◽  
Experimental Evaluation ◽  
Micro Hardness ◽  
Aisi 304 ◽  
Torsional Strength ◽  
Hardness Values

AbstractThe present study emphasizes on joints two industrially important materials AISI 304 with AISI 1021steels, produced by friction welding have been investigated. Samples were welded under different axial pressures ranging from 75MPa to 135MPa, at constant speed of 920rpm. The tensile strength, torsional strength, impact strength and micro hardness values of the weldments were determined and evaluated. Simultaneously the fractrography of the tensile tested specimens were carried out, so as to understand the failure analysis. It was observed that improved mechanical properties were noticed at higher axial pressures. Ductile failures of weldments were also observed at 120MPa and 135MPa axial pressures during fractography analysis.

Sign in / Sign up

Export Citation Format

Share Document