EFFECT OF TEMPERATURE AND IRRADIATION DOSE OF He+ AND N+ IONS ON SURFACE SWELLING AT GRAIN INTERIOR AND GRAIN BOUNDARY IN TYPE 316 STAINLESS STEEL

2004 ◽  
Vol 03 (06) ◽  
pp. 765-773 ◽  
Author(s):  
L. LIU ◽  
T. MITAMURA ◽  
M. TERASAWA ◽  
A. YAMAMOTO ◽  
H. TSUBAKINO
Keyword(s):  
Stainless Steel ◽  
Grain Boundaries ◽  
High Temperatures ◽  
Irradiation Dose ◽  
Surface Deformation ◽  
Ion Irradiation ◽  
Void Formation ◽  
Step Height ◽  
Effect Of Temperature ◽  
High Doses

Austenitic stainless steel specimens of type 316SS were irradiated by 200 keV He + ions or 200 keV N + ions. Atomic force microscopy (AFM) and transmission electron microscopy (TEM) were employed to study the fine surface deformation of the irradiated specimens. At the high temperatures of He + ion irradiation, distinct swelling was observed at grain interior and grain boundaries by AFM and helium bubbles were found by TEM. It is suggested that helium atoms agglomerate in high doses and high temperatures. The nanometer-level step height of surface swelling induced by He + ion irradiation has obvious dependence on the irradiation dose and temperature. In the case of N + ion irradiation, the swelling was observed at grain interior but the step height was less remarkable than in the case of He + ions. The swelling is induced by void formation. The caved-in grain boundaries were recognized in N + ion irradiated area.

Characterization of oxide particles in ODS austenitic stainless steel after heavy ion irradiation up to high doses

2011 ◽  
Vol 1298 ◽  
Author(s):  
Hiroshi Oka ◽  
Yosuke Yamazaki ◽  
Hiroshi Kinoshita ◽  
Naoyuki Hashimoto ◽  
Somei Ohnuki ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Ion Irradiation ◽  
Hot Extrusion ◽  
Oxide Dispersion Strengthened ◽  
Complex Oxide ◽  
Heavy Ion ◽  
Oxide Particles ◽  
The Difference ◽  
High Doses

ABSTRACTOxide dispersion strengthened austenitic stainless steel (ODS316), which is based on advanced SUS316 steel, has been developed by mechanically alloying and hot extrusion. Hafnium and titanium were added to make a fine distribution of oxide particles. The stability of oxide particles dispersed in ODS316 under irradiation was evaluated after 250 keV Fe+ irradiation up to high doses at 500 °C. TEM observation and EDS analysis indicated that fine complex oxide particles with Y, Hf and Ti were mainly dispersed in the matrix. There are no significant changes in the distribution and the size of oxide particles after irradiation. It was also revealed that the constitution ratio of Ti in complex oxide appeared to be decreased after irradiation. This diffuse-out of Ti during irradiation could be explained by the difference in oxide formation energy among alloying elements.

Crystal defects responsible for mechanical behaviors of a WC–Co composite at room and high temperatures – a simulation study

2019 ◽  
Vol 75 (2) ◽  
pp. 134-142 ◽  
Author(s):  
Jing Fang ◽  
Xuemei Liu ◽  
Hao Lu ◽  
Xingwei Liu ◽  
Xiaoyan Song
Keyword(s):  
Plastic Deformation ◽  
Grain Boundaries ◽  
High Temperatures ◽  
Boundary Migration ◽  
Strain Curve ◽  
Crystal Defects ◽  
Effect Of Temperature ◽  
Triple Junctions ◽  
Deformation Processes ◽  
Increasing Temperature

The microstructure evolution and changes in the structures of crystal defects of the nanocrystalline WC–Co composite in the process of uniaxial compression were studied by simulations at both room and high temperatures. The deformation processes were demonstrated as a function of stress and temperature for the stages prior to and after yielding of the composite. The Peierls stresses were evaluated for Co and WC dislocations with increasing temperature. The deformation mechanisms for each stage of the stress–strain curve were disclosed, in which the effect of temperature was clarified. It was found that with the increase of stress, from elastic deformation to plastic deformation then to yielding of the composite, the dominant mechanisms are grain boundary migration, formation and motion of dislocations in Co, concurrent motion and reaction of dislocations in Co and WC, and then rotation of WC grains in combination with motion of Co and WC dislocations. At the yielding stage, sliding of WC grain boundaries plays an increasingly important role in the contribution to plastic deformation at high temperatures. With strain the proportion of mobile dislocations decreases, and dislocations pile up at triple junctions of WC grains, WC/WC grain boundaries and WC/Co phase boundaries in priority order, leading to the nucleation and propagation of microcracks in these regions.

scholarly journals Energy Coupling of Laser Radiation on AISI 304 Stainless Steel: Effect of High Temperatures and Surface Oxidation

Materials ◽  
2019 ◽  
Vol 12 (17) ◽  
pp. 2802 ◽  
Author(s):  
Hipp ◽  
Mahrle ◽  
Beyer
Keyword(s):  
Stainless Steel ◽  
Melting Point ◽  
High Temperatures ◽  
Coupling Efficiency ◽  
Surface Oxidation ◽  
Energy Coupling ◽  
304 Stainless Steel ◽  
Effect Of Temperature ◽  
Laser Material Processing ◽  
Laser Materials

The industrial application of laser materials processing methods is still far ahead of research into the physical phenomena occurring during these processes. In particular, the effect of high temperatures on the energy coupling of laser irradiation of metals is poorly understood. However, most processes in laser materials treatment involve temperatures above the melting point or even cause evaporation. This study therefore evaluates the effect of high temperatures on the energy coupling efficiency of stainless steel experimentally for three typical laser wavelengths (515 nm, 1.07 µm, 10.6 µm). As a result, it is shown that the effect of temperature on the energy coupling efficiency depends on the wavelength. In this context the relevance of the X-point phenomenon known from the emissivity theory could be demonstrated for laser material processing. Further, the effect of a process-induced surface oxidation is analyzed. At temperatures above 650 °C the energy coupling efficiency dramatically increases to around 65% at melting point and stays at this high level even in the liquid phase.

Solute Segregation in Stainless Steel under Irradiation

1977 ◽  
Vol 35 ◽  
pp. 46-47
Author(s):  
Edward A. Kenik
Keyword(s):  
Stainless Steel ◽  
Ion Irradiation ◽  
Three Dimensional ◽  
Void Formation ◽  
Dislocation Loops ◽  
Nickel Ion ◽  
316 Stainless Steel ◽  
Prime Concern ◽  
Radiation Induced ◽  
The Stability

Solute element additions can significantly influence the behavior of an alloy under irradiation. The aggregation of irradiation-induced vacancies into three-dimensional clusters, voids, and the volume expansion, swelling, associated with void formation is of prime concern in the design of nuclear reactors. A modified type 316 stainless steel, LS1A, has been developed which exhibits high resistance to swelling. This alloy, containing ˜1.0 wt % silicon and 0. 15 wt % titanium, swells 30 times less under nickel ion irradiation than a nominal type 316 stainless steel.In addition to the observation of swelling resistance in LS1A, it was observed that the evolution of dislocation portions of the damage structure was modified by the silicon and titanium additions. Specifically, the stability of faulted dislocation loops in LS1A is quite high and the growth of large loops is severely curtailed. At higher doses, radiation-induced precipitates of the same size and shape as the dislocation loops were observed.

Radioimmunotherapy of Xenografts of Human Pancreatic Carcinomas - Intravenous and Intratumoral Application of 131l-Labelled Monoclonal Antibodies

1986 ◽  
Vol 25 (06) ◽  
pp. 235-238 ◽  
Author(s):  
S. Lander ◽  
M. Bahlo ◽  
R. Montz ◽  
R. Klapdor
Keyword(s):  
Irradiation Dose ◽  
Tumor Regression ◽  
Whole Body ◽  
Inhibit Tumor Growth ◽  
Local Irradiation ◽  
Clinical Value ◽  
Direct Radiation ◽  
Intravenous Injections ◽  
Induce Tumor Regression ◽  
High Doses

The effects of radioimmunotherapy were tested in xenografts of 2 different human pancreatic carcinomas comparing the intravenous and intratumoral application. On principle, intravenous injections of high doses of 131l-anti- Ca 19-9 or -BW 494/32 may inhibit tumor growth. In view of the low direct radiation dose (360-2100 rad), however, other factors than direct toxic effects have to be discussed, e. g. systemic effects due to the high whole-body irradiation. Intratumoral application, however, may induce tumor regression or growth inhibition due to the high local irradiation dose. Consequently, this treatment modality might be of clinical value at least in some patients.

AK STEEL 410S

Alloy Digest ◽  
2006 ◽  
Vol 55 (5) ◽  
Keyword(s):  
Stainless Steel ◽  
Corrosion Resistance ◽  
Physical Properties ◽  
Tensile Properties ◽  
Ferritic Stainless Steel ◽  
High Temperatures ◽  
Heat Treating ◽  
Austenite Formation ◽  
Oxidation Resistant

Abstract AK Steel 410S is a fully ferritic stainless steel with elements added to retard austenite formation at high temperatures. The resulting low hardening allows for use as oxidation-resistant parts. This datasheet provides information on composition, physical properties, hardness, elasticity, and tensile properties. It also includes information on corrosion resistance as well as forming, heat treating, and joining. Filing Code: SS-964. Producer or source: AK Steel.

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