Environmentally Assisted Cracking Research of Engineering Alloys for Nuclear Waste Repository Containers

2012 ◽  
Vol 1475 ◽  
Author(s):  
Raul B. Rebak
Keyword(s):  
Stainless Steel ◽  
Carbon Steel ◽  
Nuclear Waste ◽  
Nickel Alloys ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Waste Repository ◽  
Environmentally Assisted Cracking ◽  
Waste Repository ◽  
Engineering Alloys

ABSTRACTAll the countries that operate commercial nuclear power plants are planning to dispose of the waste in underground geologically stable repositories. The materials being studied for the fabrication of the containers include carbon steel, stainless steel, copper, titanium and nickel alloys. The aim of this work is to review results from research performed using the alloys of interest regarding their resistance to environmentally assisted cracking (EAC) under simulated repository conditions. In general, it is concluded that the environments are mild and that the studied metals may not be susceptible to cracking under the planned emplacement conditions.

scholarly journals Parameters influencing the low-cycle fatigue life of materials in pressure water reactor nuclear power plants / Parametry ovlivòující únavové chování materiálù pro tlakovodní jaderné reaktory v režimu nízkocyklové únavy

2015 ◽  
Vol 59 (3) ◽  
pp. 91-98
Author(s):  
V. Šefl
Keyword(s):  
Stainless Steel ◽  
Fatigue Life ◽  
Carbon Steel ◽  
Austenitic Stainless Steel ◽  
Literature Review ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Low Cycle Fatigue ◽  
Cycle Fatigue

Abstract In this literature review we identify and quantify the parameters influencing the low-cycle fatigue life of materials commonly used in nuclear power plants. The parameters are divided into several groups and individually described. The main groups are material properties, mode of cycling and environment parameters. The groups are further divided by the material type - some parameters influence only certain kind of material, e.g. sulfur content may decreases fatigue life of carbon steel, but is not relevant for austenitic stainless steel; austenitic stainless steel is more sensitive to concentration of dissolved oxygen in the environment compared to the carbon steel. The combination of parameters i.e. conjoint action of several detrimental parameters is discussed. It is also noted that for certain parameters to decrease fatigue life, it is necessary for other parameter to reach certain threshold value. Two different approaches have been suggested in literature to describe this complex problem - the Fen factor and development of new design fatigue curves. The threshold values and examples of commonly used relationships for calculation of fatigue lives are included. This work is valuable because it provides the reader with long-term literature review with focus on real effect of environmental parameters on fatigue life of nuclear power plant materials.

scholarly journals Experimental Study on Melt Decontamination of Stainless Steel and Carbon Steel Using Induction Melting

Metals ◽  
2021 ◽  
Vol 11 (8) ◽  
pp. 1218
Author(s):  
Pengfei Zhao ◽  
Wonsub Chung ◽  
Mincheol Lee ◽  
Seokyoung Ahn
Keyword(s):  
Stainless Steel ◽  
Carbon Steel ◽  
Nuclear Power ◽  
Power Plants ◽  
Xrd Analysis ◽  
Induction Melting ◽  
Oxide Formation ◽  
Film Coatings ◽  
High Gamma ◽  
Melted Metal

Many nuclear power plants (NPP) facilities have aged and are being dismantled around the world. As a result, large amounts of radioactive metal waste are generated during decommissioning. Carbon steel, stainless steel, and Inconel are the most common metals used in NPP, and radioactive contaminants are mostly accumulated in the corrosion layer. There are various radionuclides, but the main ones are 60Co, 137Cs, 54Mn and 51Cr. 60Co is the major activated corrosion product and responsible for high gamma radiation and longer half-life (5.27 years.) also makes it the most difficult to remove. Therefore, we investigated the melt decontamination characteristics of 60Co by introducing various slags using induction melting for stainless steel and carbon steel. Cobalt plating and cobalt oxide film coatings were used as specimens instead for safety purposes. The amount of cobalt removed from the slag was analyzed by using XRF. About 11% of the cobalt was removed from the contaminated metal due to slag oxide formation. The distribution of cobalt in the melted metal was also almost homogeneous according to the XRD analysis.

scholarly journals Geodynamic Zoning For Underground Isolation Of Radioctive Waste

2015 ◽  
Vol 1 ◽  
pp. 16
Author(s):  
Vladislav Morozov ◽  
Alexander Kagan
Keyword(s):  
Radioactive Waste ◽  
Nuclear Waste ◽  
Nuclear Power ◽  
Nuclear Waste Repository ◽  
Area Selection ◽  
Deformed State ◽  
Waste Repository ◽  
Selection For ◽  
Granitoid Massif

The problem of area selection for underground isolation of radioactive waste is important for all countries using nuclear power. The paper presents the results of modeling the stress-deformed state of Nizhnekanskiy granitoid massif and shows the possibility of using such simulations for the geodynamic zoning of areas. The calculation is given to the most probable directions of groundwater filtration, which is one of the main threats for the nuclear waste repository.

Chemical, Physical and Engineering Characterization Of Candidate Backfill Clays and Clay Admixtures for a Nuclear Waste Respository-Part I

1981 ◽  
Vol 6 ◽  
Author(s):  
Sudesh K. Singh
Keyword(s):  
Nuclear Waste ◽  
Morphological Changes ◽  
Deionized Water ◽  
Engineering Properties ◽  
Nuclear Waste Repository ◽  
Exchange Cation ◽  
Mineral Components ◽  
Waste Repository ◽  
Mineralogical Compositions

ABSTRACTFourteen Canadian clays and clay admixtures were subjected to simulated nuclear waste repository environments. The present work is concerned with the montmorillonite-dominant materials only. The montmorillonite-dominant samples showed significant leaching on interaction with deionized water. On heating the samples at 200°C for 500 hours, montmorillomites lost intermicellar water completely and acquired cusp-like to cylindrical morphologies. The loss of water and the morphological changes in montmorillonites significantly altered the engineering characteristics. Permeability, shrinkage limits, compactability and shear strength varied in response to the dominant exchange cation in the structure of montmorillonites and the presence of other mineral components in the materials. The synthetic granite water reacted with montmorillonites and led to changes in chemical and mineralogical compositions, crystalline state and engineering properties.

Modelling of thermal rock mass properties at the potential sites of a Swedish nuclear waste repository

2009 ◽  
Vol 46 (6) ◽  
pp. 1042-1054 ◽  
Author(s):  
Jan Sundberg ◽  
Pär-Erik Back ◽  
Rolf Christiansson ◽  
Harald Hökmark ◽  
Märta Ländell ◽  
...  
Keyword(s):  
Rock Mass ◽  
Nuclear Waste ◽  
Nuclear Waste Repository ◽  
Rock Mass Properties ◽  
Mass Properties ◽  
Waste Repository
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