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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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At least 973 records · Page 54
All sourcesNASA NTRSDOE OSTI
DOE OSTI2026

Mechanical Behavior of Neutron Irradiated Refractory Multi-Principal Element Alloys Processed via Spark Plasma Sintering

The search for advanced materials capable of withstanding the extreme conditions of Generation IV reactors is a critical area in materials science research. These reactors operate under severe environments, including high temperatures, corrosion, stress, and irradiation damage. Consequently, there is a need for innovative alloy systems to ensure the reliability and longevity of proposed Generation IV reactor components. Refractory multi-principal-element alloys (RMPEA) have emerged as a promising candidate due to their exceptional properties. These alloys, characterized by their composition of multiple principal elements in near-equiatomic ratios, exhibit superior resistance to irradiation damage, reduced void swelling, enhanced microstructural stability, and minimal irradiation-induced hardening. While initial studies on RMPEAs have shown promising results, most research has been limited to thin films, nanocrystalline microstructures, and ion irradiation, which do not accurately represent the behavior of bulk materials. To address this gap, our research focused on the neutron irradiation of bulk RMPEAs. We aim to conduct comprehensive post-irradiation examinations (PIE) of RMPEAs irradiated at the Advanced Test Reactor at Idaho National Laboratory. The RMPEAs were synthesized using spark plasma sintering (SPS) with mechanically alloyed metallurgical powder. The RMPEA specimens are a MoNbTi alloy system with additions of -Zr, and -ZrV. Furthermore, PIE consisted of mechanical testing and advanced materials characterization. The mechanical testing consisted of sub-sized tensile testing, micro- and nano- indentation. Microstructural characterization included scanning electron microscopy and transmission electron microscopy. Mechanical testing coupled with advanced microscopy techniques provides insight into phase morphology and its effects on the mechanical properties of the RMPEA specimens. The results indicate that both pristine and irradiated RMPEA specimens exhibited brittle behavior during tensile testing, which can be attributed to their heterogeneous microstructure. The SPS manufacturing process did not include any post treatment, which resulted in a heterogeneous microstructure. Energy-dispersive X-ray spectroscopy revealed the presence of intermetallic such as laves phases within the microstructure. Specifically, Ti-rich precipitates were observed in the MoNbTi specimen, while Mo-rich precipitates were found in the MoNbTiZrV specimen. Nano-hardness testing of pristine samples showed that the laves phases exhibited higher hardness values compared to the matrix phase, suggesting that precipitate hardening is likely the dominant hardening mechanism in these specimens. The results from this work will be used to build a finite element model to predict mechanical behavior of future MPEA compositions. Thus, enabling for a streamlined approach to developing novel MPEAs for the nuclear industry.

36 - MATERIALS SCIENCE↗
DOE OSTI2014

Analysis of Phase Transformation Studies in Solute Addition Alloys

Components serving in a nuclear reactor plant must withstand a very harsh environment including extended time at elevated temperatures, neutron irradiation, stress, and/or corrosive media. The many modes of degradation are complex and very depending on material and service locations. However, understanding and managing materials degradation is paramount for the continued safe and reliable operation of nuclear power plants. For the reactor core and primary systems, several key areas have been identified. Thermomechanical considerations such as aging and fatigue must be examined. Irradiation-induced processes must also be considered for higher fluences under the life extension consideration of the current light water reactors (LWRs), which particularly includes the influence of radiation-induced segregation (RIS), swelling, and precipitation on component hardening and embrittlement. Corrosion takes many forms within the reactor core, although irradiation-assisted stress corrosion cracking (IASCC) and primary water stress corrosion cracking (PWSCC) are of high interest in extended life scenarios. Research in these areas can build upon other ongoing programs in the LWR industry as well as other reactor materials programs (such as fusion and fast reactors) to help resolve these issues for extended LWR life. Type 304 and 316 stainless steels are classic structural materials used in LWRs. A set of well designed type 304 and 316 variants by changing the amount of a single solute element were irradiated using the BOR-60 fast breeder reactor at ~320°C in Russia. This set of alloy samples has been used in this task to characterize detailed microstructural evolution and measure magnetic phase, swelling and hardness. This report summarizes the detailed microstructural results, characterized using conventional and scanning transmission electron microscopy (CTEM/STEM) and energy dispersive X-ray spectroscopy (EDS), and the newly developed model of strength factor for estimating radiation hardening. The results provide invaluable insights into understanding degradation mechanisms of key components and assists in the prediction of the life of similar materials and the base knowledge required to develop advanced radiation resistant alloys. The effect of solute elements on microstructural evolution under neutron irradiation is explored. The approximate correlation between microstructure changes and radiation hardening is established. The major results and implications are discussed below.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2019

Research on the Corrosion Behavior of X70 Pipeline Steel Under Coupling Effect of AC + DC and Stress

The coupling effect of stray AC (alternating current) + DC (direct current) and tensile stress-induced X70 pipeline corrosion is complicated with its mechanism uncovered. In this work, the corrosion behavior of X70 pipeline steel under three different corrosion (including an individual AC corrosion, mixed AC + 150 MPa tensile stress corrosion, coupling effect of AC + a 30 A/m{sup 2} DC interference and 150 MPa tensile stress corrosion) conditions in Dagang soil simulated solution was investigated by COMSOL Multiphysics software simulation, electrochemical tests, scanning electron microscope and other techniques. The results indicated that with the increase in AC density, the open-circuit potential of the X70 steel samples was negatively shifted and corrosion rate increased in three different corrosion conditions. The corrosion rates of X70 steel samples under individual AC interference were almost unchanged when 150.9 MPa tensile stress was applied. When applying 30 A/m{sup 2} DC interference, the corrosion rate of X70 steel increases significantly. Therefore, the factors affecting corrosion performance of X70 pipeline steel were DC > AC > stress. Under individual AC interference, uniform corrosion occurred on the X70 steel at an AC current density of less than 30 A/m{sup 2}, while the pitting corrosion occurred at an AC current density of greater than 100 A/m{sup 2}. The application of tensile stress and DC had a certain inhibitory effect on pitting corrosion.

36 MATERIALS SCIENCE↗
DOE OSTI2018

Effect of Laser Shock Peening on Residual Stress, Microstructure and Hot Corrosion Behavior of Damage-Tolerant TC21 Titanium Alloy

The effect of laser shock peening (LSP) on the residual stress, microstructure and hot corrosion behavior of damage-tolerant TC21 alloy was investigated. The equilateral scanning pattern was adopted to obtain a large overlapping area for LSP. The hot corrosion experiments in a salt mixture composed of 75 wt.% Na{sub 2}SO{sub 4} + 25 wt.% NaCl at 700 and 800 °C for a total exposure of 25 h were conducted. The results demonstrated that LSP caused a high compressive residual stress with a significant increase in micro-hardness and microstructural changes in the form of crystal defects, i.e., high density dislocations. The crystal defects promoted the outward diffusion of Al, Cr and Ti to form protective mixed oxides (Al, Cr, Ti)O{sub 2}. These oxides improved the adhesion of outer oxide layer and hindered the inward diffusion of O, S and Cl, which was beneficial to improve hot corrosion resistance. The mass gains of LSP-treated specimens after hot corrosion at 700 and 800 °C were, respectively, 3.72 and 4.78 mg/cm{sup 2}, which were much lower than those of untreated specimens (5.65 and 6.81 mg/cm{sup 2}). Therefore, LSP leads to an improvement in resistance to hot corrosion of TC21 alloy.

36 MATERIALS SCIENCE↗
NASA NTRS1985

Internal stresses in wear and corrosion resistant amorphous metallic coatings of (W/0.6/Re/0.4/)76B24 and (Mo/0.6/Ru/0.4/)82B18

Hard protective coatings in the W-Re-B and Mo-Ru-B alloy systems have been deposited by magnetron sputtering onto soda-lime glass and heat-treated AISI 52100 steel substrates. X-ray diffraction has confirmed the amorphous nature of the as-deposited coatings, and their crystallization temperatures were determined by differential thermal analysis to be 1000 and 790 C for W-Re-B and Mo-Ru-B coatings, respectively. Both coatings exhibit high microhardness; Mo-Ru-B, in addition, has excellent corrosion resistance by comparison with pure Mo at high anodic potentials. Attention is given to the influence of internal stresses on the protective properties of the coatings deposited under different conditions.

Thakoor, A. P.↗
DOE OSTI2017

A nanomechanical Raman spectroscopy based assessment of stress distribution in irradiated and corroded SiC

Silicon carbide (SiC) composites are under consideration for cladding and structural materials in various types of reactors. The effects of ion irradiation and corrosion on stress distribution due to mechanical loading on chemical vapor deposited (CVD) SiC were investigated here in this paper by using nanomechanical Raman spectroscopy (NMRS). The stress distribution was analyzed as a function of the oxide formation on a corroded specimen and as a function of ion-induced irradiation damage in an irradiated specimen. A finite element method (FEM) based model was developed based on local mechanical properties measured using nanoindentation to predict the NMRS measured stress distribution. The stress distribution was also predicted theoretically by using a stress concentration factor, which is a function of sample geometry and boundary conditions. The maximum stress obtained theoretically was in good agreement with the FEM model and NMRS based measurements. FEM results captured the stress variation trends and maximum stress value in the analyzed samples. NMRS measurements predicted that corrosion had a greater influence on increasing the maximum value of stress in comparison to ion irradiation. The increase in stress attributed to corrosion in comparison to ion irradiated samples was approximately 10%–20%.

36 MATERIALS SCIENCE↗
DOE OSTI2022

Effect of Applied Stress on the Selective Oxidation of Alloy 600 Exposed to PWR Primary Water and Rhines Pack Environments

A mechanistic understanding of corrosion and oxidation processes is crucial to ensure long-term resistance to stress corrosion cracking of Ni-base structural alloys in pressurized water reactor (PWR) primary and secondary systems. Aqueous corrosion of Ni-base alloys under PWR primary water conditions was previously compared to gaseous oxidation with comparable oxygen potentials. However, those studies considered only stress-free conditions, which removes a critical parameter for understanding stress corrosion behaviors. A significant knowledge gap exists for the role of applied stresses on selective internal oxidation in gaseous environments. A micro-4-point-bend jig was designed to facilitate stress in a Rhines Pack set-up. Selective oxidation at different stress and strain conditions was investigated in a series of Rhines Pack experiments for Alloy 600. Focused ion beam milling enabled the extraction of site-specific specimens containing selected high-energy grain boundaries from tensile and compressive stress regions. Analytical transmission electron microscopy was employed to analyze the microstructure and chemical composition of the resulting oxides. Protective surface oxide films and selective intergranular oxides were observed at different conditions. The implications of these fundamental differences are discussed relative to intergranular attack and stress corrosion cracking mechanisms in PWR primary water.

stress, 4-point-bend, selective oxidation, Alloy 6↗
DOE OSTI2017

Corrosion Behavior of Aqua-Blasted and Laser-Engraved Type 316L Stainless Steel

The effect of aqua blasting and laser engraving on surface microstructure development, residual stress and corrosion resistance of type 316L stainless steel has been investigated. Aqua blasting resulted in a deformed near-surface microstructure containing compressive residual stresses. Subsequent laser engraving produced a surface layer with tensile residual stresses reaching to a depth of 200 microns. Changes of surface roughness topography were accompanied by the development of a thick oxide/hydroxide film after laser engraving. The atmospheric corrosion behavior of all surfaces with MgCl{sub 2}-laden droplets was compared to their electrochemical response in 1M NaCl and 0.7 M HCl aqueous solutions. The measured total volume loss after atmospheric corrosion testing was similar for all investigated surface conditions. Laser-engraved surface exhibited the smallest number of corrosion sites, but the largest mean corrosion depth.

36 MATERIALS SCIENCE↗
DOE OSTI2019

Mechanical Properties and Corrosion Behavior of Spray-Formed 7075 Alloy with One-Stage Aging

The mechanical properties, corrosion resistance and microstructure of the spray-formed 7075 alloy after one-stage aging treatments were studied by using a tensile tester, hardness tester, slow strain rate test, electrical test, intergranular corrosion test, electrochemical corrosion test, scanning electron microscope and transmission electron microscope. The results show that the strength and hardness of the alloy have double peaks with the one-stage aging treatments. With aging at 120 °C for 24 h (first peak), abundant tiny η′ phases and η phases precipitate in the matrix. The tensile strength of the alloy increases to 760 MPa, and the elongation is 4.8%. After aging at 120 °C for 132 h (second peak), blocky η phases appear. The tensile strength and elongation of the alloy are 757 MPa and 5.9%, respectively. The grain boundary precipitates dissociate, and the precipitate-free zones are widened. The corrosion resistance of the alloy increases.

36 MATERIALS SCIENCE↗
NASA NTRS1981

Effects of environmental variables on the crack initiation stages of corrosion fatigue of high strength aluminum alloys

Fatigue initiation in six aluminum alloys used in the aircraft industry was investigated. Cyclic loading superimposed on a constant stress was alternated with atmospheric corrosion. Tests made at different stress levels revealed that a residual stress as low as 39% of the yield strength caused stress corrosion cracking in some of the alloys. An atmospheric corrosion rate meter developed to measure the corrosivity of the atmosphere is described. An easily duplicated hole in the square test specimen with a self-induced residual stress was developed.

Poteat, L. E.↗
DOE OSTI2018

Friction Stir Welding of Dissimilar Al/Al and Al/Non-Al Alloys: A Review

Friction stir welding is a solid-state welding technique that has many advantages over traditional fusion welding, and has been widely adopted in the aerospace and automotive industries. This article reviews research developments in friction stir welding of dissimilar alloys systems, including combinations of aluminum alloys with Mg alloys, Cu, and steel. Microstructural evolution, hardness, tensile and fatigue properties, residual stresses, and corrosion behavior of dissimilar welds will be reported. The effects of processing parameters such as tool rotation and traverse speeds, tool position, material position, and tool geometry on the weld quality are also presented. Discussions on future research directions in friction stir welding will also be provided in the context of existing literature and future high-integrity applications.

36 MATERIALS SCIENCE↗
DOE OSTI2018

Electrochemical Behavior of Biomedical Titanium Alloys Coated with Diamond Carbon in Hanks’ Solution

Biomedical implants in the knee and hip are frequent failures because of corrosion and stress on the joints. To solve this important problem, metal implants can be coated with diamond carbon, and this coating plays a critical role in providing an increased resistance to implants toward corrosion. In this study, we have employed diamond carbon coating over Ti-6Al-4V and Ti-13Nb-13Zr alloys using hot filament chemical vapor deposition method which is well-established coating process that significantly improves the resistance toward corrosion, wears and hardness. The diamond carbon-coated Ti-13Nb-13Zr alloy showed an increased microhardness in the range of 850 HV. Electrochemical impedance spectroscopy and polarization studies in SBF solution (simulated body fluid solution) were carried out to understand the in vitro behavior of uncoated as well as coated titanium alloys. The experimental results showed that the corrosion resistance of Ti-13Nb-13Zr alloy is relatively higher when compared with diamond carbon-coated Ti-6Al-4V alloys due to the presence of β phase in the Ti-13Nb-13Zr alloy. Electrochemical impedance results showed that the diamond carbon-coated alloys behave as an ideal capacitor in the body fluid solution. Moreover, the stability in mechanical properties during the corrosion process was maintained for diamond carbon-coated titanium alloys.

36 MATERIALS SCIENCE↗