Some problems in the mechanical testing of structural materials under neutron irradiation

1969 ◽  
Vol 1 (3) ◽  
pp. 217-221
Author(s):  
G. S. Pisarenko ◽  
V. N. Kiselevskii
Keyword(s):  
Mechanical Testing ◽  
Neutron Irradiation ◽  
Structural Materials

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 Additive Manufacturing of structural materials for nuclear application and rapid mesoscale mechanical testing

2021 ◽  
Vol 27 (S1) ◽  
pp. 2154-2155
Author(s):  
Peter Hosemann ◽  
Jason Duckering ◽  
Andrew Dong ◽  
Jeff Bickel ◽  
Stuart Maloy ◽  
...  
Keyword(s):  
Additive Manufacturing ◽  
Mechanical Testing ◽  
Structural Materials

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 Method and installation for investigating the resistance of structural materials to cyclic loading under neutron irradiation

1985 ◽  
Vol 17 (8) ◽  
pp. 1131-1134
Author(s):  
V. N. Kiselevskii ◽  
D. F. Kharitonov ◽  
N. P. Stepchuk ◽  
A. G. Alyab'ev
Keyword(s):  
Cyclic Loading ◽  
Neutron Irradiation ◽  
Structural Materials
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