• Title/Summary/Keyword: c-type dislocation

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Shoulder Replacement Arthroplasty after Failed Proximal Humerus Fracture (상완골 근위부 골절의 치료 실패 후 견관절 치환술)

  • Park, Jin-Young;Seo, Beom-Ho;Lee, Seung-Jun
    • Journal of the Korean Orthopaedic Association
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    • v.54 no.2
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    • pp.110-119
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    • 2019
  • Proximal humerus fracture can be defined as a fracture that occurs in the surgical neck or proximal part of the humerus. Despite the appropriate treatment, however, various complications and sequelae can occur, and the treatment is quite difficult often requiring surgical treatment, such as a shoulder replacement. The classification of sequelae after a proximal humerus fracture is most commonly used by Boileau and can be divided into two categories and four types. Category I is an intracapsular impacted fracture that is not accompanied by important distortions between the tuberosities and humeral head. An anatomic prosthesis can be used without greater tuberosity osteotomy. In category I, there are type 1 with cephalic collapse or necrosis with minimal tuberosity malunion and type 2 related to locked dislocation or fracture-dislocation. Category II is an extracapsular dis-impacted fracture with gross distortion between the tuberosities and the humeral head. To perform an anatomic prosthesis, a tuberosity osteotomy should be performed. In category II, there are type 3 with nonunion of the surgical neck and type 4 with severe tuberosity malunion. In type 1, non-constrained arthroplasty (NCA) without a tuberosity osteotomy should be considered as a treatment. On the other hand, reverse shoulder arthroplasty (RSA) should be considered if types 1C or 1D accompanied by valgus or varus deformity or severe fatty degeneration of the rotator cuff. In general, the results are satisfactory when NCA is performed in type 2 sequelae. On the other hand, RSA can be considered as an option when there is no bony defect of the glenoid and a defect of the rotator cuff is accompanied. In type 3, it would be effective to perform internal fixation with a bone wedge graft rather than shoulder replacement arthroplasty. Recent reports on the results of RSA are also increasing. On the other hand, recent reports suggest that good results are obtained with RSA in type 3. In type 4, RSA should be considered as a first option.

Damping Capacities of Nonthermoelastic BCC and HCP Martensites of Fe-Mn Binary System (Fe-Mn 이원계에서 비열탄성형 BCC 마르텐사이트와 HCP 마르텐사이트의 진동감쇠능)

  • Choi, C.S.;Kim, J.D.;Moon, I.G.;Baik, S.H.
    • Journal of the Korean Society for Heat Treatment
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    • v.4 no.4
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    • pp.15-23
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    • 1991
  • The damping capacities of the nonthermoelastic bcc type lath martensite and of the nonthermoelastic hcp type thin plate martensite in Fe-Mn alloys were studied. Fe-17%Mn alloy showing the hcp type thin plate martensite was superior to Fe-4%Mn alloy having the bcc type lath martensite in damping capacity. The damping capacity of the Fe-17%Mn alloy became greater with increasing the hcp martensite volume fraction. The damping mechanism of the Fe-4%Mn alloy was well explained by the dislocation model. However, the damping mechanism of the Fe-17%Mn alloy was explained on the basis of austenite/martensite interface moving model. The two alloys showed almost same levels of tensile strength. However, the elongation was greater in the Fe-17%Mn alloy than in the Fe-4%Mn alloy, showing lower yield strength in the former than in the latter. This result was considered to be attributed to formation of stress-induced martensite during tension test.

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Effect of Strain Aging on the Tensile Properties of an API X70 Linepipe Steel (API X70 라인파이프강의 인장 특성에 미치는 변형 시효의 영향)

  • Lee, Seung-Wan;Lee, Sang-In;Hwang, Byoungchul
    • Korean Journal of Materials Research
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    • v.27 no.10
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    • pp.524-529
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    • 2017
  • The effect of strain aging on the tensile properties of API X70 linepipe steel was investigated in this study. The API X70 linepipe steel was fabricated by controlled rolling and accelerated cooling processes, and the microstructure was analyzed using optical and scanning electron microscopes and electron backscatter diffraction. Strain aging tests consisting of 1 % pre-strain and thermal aging at $200^{\circ}C$ and $250^{\circ}C$ were conducted to simulate U-forming, O-forming, Expansion(UOE) pipe forming and anti-corrosion coating processes. The API X70 linepipe steel was composed of polygonal ferrite, acicular ferrite, granular bainite, and bainitic ferrite whose volume fraction was dependent on the chemical composition and process conditions. As the thermal aging temperature increased, the steel specimens showed more clearly discontinuous type yielding behavior in the tensile stress-strain curve due to the formation of a Cottrell atmosphere. After pre-strain and thermal aging, the yield and tensile strengths increased and the yield-to-tensile strength ratio decreased because yielding and aging behaviors significantly affected work hardening. On the other hand, uniform and total elongations decreased after pre-strain and thermal aging since dislocation gliding was restricted by increased dislocation density after a 1 % pre-strain.

RF-magnetron sputtering 방법으로 성장시킨 Ga-doped ZnO 박막의 성장 온도 변화에 따른 영향

  • Kim, Yeong-Lee;U, Chang-Ho;An, Cheol-Hyeon;Bae, Yeong-Suk;Gong, Bo-Hyeon;Kim, Dong-Chan;Jo, Hyeong-Gyun
    • Proceedings of the Korean Institute of Electrical and Electronic Material Engineers Conference
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    • 2009.06a
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    • pp.9-9
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    • 2009
  • 1 wt % Ga-dope ZnO (ZnO:Ga) thin films with n-type semiconducting behavior were grown on c-sapphire substrates by radio frequency magnetron sputtering at various growth temperatures. The room temperature grown ZnO:Ga film showed the faint preferred orientation behavior along the c-axis with small domain size and high density of stacking faults, despite limited surface diffusion of the deposited atoms. The increase in the growth temperature in the range between $300\sim550^{\circ}C$ led to the granular shape of epitaxial ZnO:Ga films due to not enough thermal energy and large lattice mismatch. The growth temperature above $550^{\circ}C$ induced the quite flat surface and the simultaneous improvement of electrical carrier concentration and carrier mobility, $6.3\;\times\;10^{18}/cm^3$ and $27\;cm^2/Vs$, respectively. In addition, the increase in the grain size and the decrease in the dislocation density were observed in the high temperature grown films. The low-temperature photoluminescence of the ZnO:Ga films grown below $450^{\circ}C$ showed the redshift of deep-level emission, which was due to the transition from $Zn_j$ to $O_i$ level.

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Semi-insulation Behavior of GaN Layer Grown on AlN Nucleation Layer

  • Lee, Min-Su;Kim, Hyo-Jeong;Lee, Hyeon-Hwi
    • Proceedings of the Korean Vacuum Society Conference
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    • 2011.08a
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    • pp.132-132
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    • 2011
  • The sheet resistance (Rs) of undoped GaN films on AlN/c-plane sapphire substrate was investigated in which the AlN films were grown by R. F. magetron sputtering method. The Rs was strongly dependent on the AlN layer thickness and semi-insulating behavior was observed. To clarify the effect of crystalline property on Rs, the crystal structure of the GaN films has been studied using x-ray scattering and transmission electron microscopy. A compressive strain was introduced by the presence of AlN nucleation layer (NL) and was gradually relaxed as increasing AlN NL thickness. This relaxation produced more threading dislocations (TD) of edge-type. Moreover, the surface morphology of the GaN film was changed at thicker AlN layer condition, which was originated by the crossover from planar to island grains of AlN. Thus, rough surface might produce more dislocations. The edge and mixed dislocations propagating from the interface between the GaN film and the AlN buffer layer affected the electric resistance of GaN film.

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The Effect of Microstructures on Yield Strength and Impact Properties of a Microalloyed Steel (미세합금강의 조직이 항복강도와 충격치에 미치는 영향)

  • Jo, Jong-Chun;Werner Osterler
    • 한국기계연구소 소보
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    • s.16
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    • pp.29-39
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    • 1986
  • Several heat treatment were applied to on HSLA steel of type StE47 (German standard) to produce five ferrite microstructures of different strength and at least two different grain sizes respectively. Whereas the ferrite microstructure had a strong influence on yield strength the effect of grain size was negligible. The different strength levels could be explained by regarding the arrangement of dislocations and vanadium carbide particles, and their mutual interaction. Specimens tranformed at $600^{\circ}C$ showed the highest strength levels. In this case precipitation has occured after the $\gamma$- $\alpha$ transformation. Very small VC particles are arranged mostly along dislocation lines. Increasing both, grain size and pearlite volume fraction leads to a remarkable shift of transition temperature which was further enhanced by increasing ferrite strength.

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Effects of Annealing and Neutron Irradiation on Micostructural and Mechanical Properties of High Burn-up Zr Claddings (고연소도 신형 Zr피복관의 미세조직과 기계적 특성에 미치는 열처리 및 중성자 조사의 영향)

  • Baek, Jong Hyuk;Kim, Hyun Gil;Jeong, Yong Hwan
    • Journal of the Korean Society for Heat Treatment
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    • v.17 no.3
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    • pp.151-164
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    • 2004
  • The changes of microstructural and mechanical properties were evaluated for the high burn-up fuel claddings after the neutron irradiation of $1.8{\sim}3.1{\times}10^{20}n/cm^2$ (E>1.0 MEV) in HANARO research reactor. After the irradiation, the spot-type dislocations (a-type dislocations) were easily observed in most claddings, and the density of the dislocations was different depending on the grains and was higher at grain boundaries than within grains. As the final annealing temperature increased, the density of spot-type dislocations increased and the line-type dislocations (c-type dislocations) which was perpendicular to the <0002> direction, appeared sporadically in some claddings. However, the types of precipitates in the fuel claddings after the irradiation were not changed from that in unirradiated claddings. The mechanical properties including the hardness, strength and elongation after the irradiation were changed due to the formation of spot-type dislocations. That is, the increase in hardness and strength as well as the decrease in elongation after the irradiation was occurred simultaneously with increasing the final annealing temperature. Owing to the Nb contribution to the formation of spot-type dislocation during the irradiation, the increase in hardness and strength in higher Nb-contained Zr alloys after the irradiation was higher than that in lower Nb-contained Zr alloys.

TEM Observation of Microstructure in Al-Sc alloys (투과전자현미경에 의한 Al-Sc합금의 미세구조 관찰)

  • 이영호;문정호;이갑호;이명현;서원선
    • Proceedings of the Materials Research Society of Korea Conference
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    • 2003.11a
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    • pp.44-44
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    • 2003
  • Scandium을 소량 첨가한 Al합금은 용체화 처리 후 시효에 의해 강화되며, 합금의 주 강화상은 Ll2 type의 규칙구조를 갖는 A1$_3$Sc상으로 열처리시 아주 미세한 정합의 구형입자로 석출한다. Scandium은 Al합금에서 첨가원소의 at%에 따른 경량화 효과가 Gold 다음으로 크다. 현재까지의 Al-Sc계 합금에 대한 연구는 시효경화에 따른 기계적 특성 변화에 대해서만 이루어져 왔으나 본 연구에서는 투과전자현미경을 이용하여 열처리에 따른 미세조직의 변화, 급냉 상태에서 생성된 A13Sc입자의 형성 및 계면구조, 시효에 따른 석출거동을 규명하였다. 실험에 사용된 alloy는 미국의 Ashurst 사에서 제조된 Al-2wt%Sc모합금과 순도 99.9%의 Al을 혼합하여 Arc melting법으로 제조하였다. Primary A13Sc상은 Ll2 type으로 응고시에 용융상태에서 먼저 핵생성되어 Al의 핵생성 site로 작용한다. 635$^{\circ}C$에서 용체화 처리한 시편에서는 수백 nm 크기를 갖는 $Al_3$Sc상이 계면과 matrix내에 구형으로 존재함을 확인하였다. 수백 nm 크기의 $Al_3$Sc상의 내부에는 역위상 경계(Antiphase boundary)이 존재로 인한 특징적인 contrast가 관찰되었으며, 이 $Al_3$Sc상은 응고시 생성된 작은 $Al_3$Sc상들이 모여져 생성된 것으로 추측된다. 수백 nm 크기 의 $Al_3$Sc사와 Al matrix 사이의 계면에는 격자상수 차이에 의한 많은 edge dislocation들이 관찰된다.

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The formation mechanism of grown-in defects in CZ silicon crystals based on thermal gradients measured by thermocouples near growth interfaces

  • Abe, Takao
    • Journal of the Korean Crystal Growth and Crystal Technology
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    • v.9 no.4
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    • pp.402-416
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    • 1999
  • The thermal distributions near the growth interface of 150nm CZ crystals were measured by three thermocouples installed at the center, middle (half radius) and edge (10nm from surface) of the crystals. The results show that larger growth rates produced smaller thermal gradients. This contradicts the widely used heat flux balance equation. Using this fact, it is confirmed in CZ crystals that the type of point defects created is determined by the value of the thermal gradient(G) near the interface during growth, as already reported for FZ crystals. Although depending on the growth systems the effective length of the thermal gradient for defect generation are varied, we defined the effective length as 10n,\m from th interface in this experiment. If the G is roughly smaller than 20C/cm, vacancy rich CZ crystals are produced. If G is larger than 25C/cm, the species of point defects changes dramatically from vacancies to interstitials. The experimental results after detaching FZ and CZ crystals from the melt show that growth interfaces are filled with vacancies. We propose that large G produces shrunk lattice spacing and in order to relax such lattice excess interstitials are necessary. Such interstitials recombine with vacancies which were generated at the growth interface, nest occupy interstitial sites and residuals aggregate themselves to make stacking faults and dislocation loops during cooling. The shape of the growth interface is also determined by te distributions of G across the interface. That is, the small G and the large G in the center induce concave and convex interfaces to the melts, respectively.

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Atomistic simulations of defect accumulation and evolution in heavily irradiated titanium for nuclear-powered spacecraft

  • Hai Huang;Xiaoting Yuan;Longjingrui Ma;Jiwei Lin;Guopeng Zhang;Bin Cai
    • Nuclear Engineering and Technology
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    • v.55 no.6
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    • pp.2298-2304
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    • 2023
  • Titanium alloys are expected to become one of the candidate materials for nuclear-powered spacecraft due to their excellent overall performance. Nevertheless, atomistic mechanisms of the defect accumulation and evolution of the materials due to long-term exposure to irradiation remain scarcely understood by far. Here we investigate the heavy irradiation damage in a-titanium with a dose as high as 4.0 canonical displacements per atom (cDPA) using atomistic simulations of Frenkel pair accumulation. Results show that the content of surviving defects increases sharply before 0.04 cDPA and then decreases slowly to stabilize, exhibiting a strong correlation with the system energy. Under the current simulation conditions, the defect clustering fraction may be not directly dependent on the irradiation dose. Compared to vacancies, interstitials are more likely to form clusters, which may further cause the formation of 1/3<1210> interstitial-type dislocation loops extended along the (1010) plane. This study provides an important insight into the understanding of the irradiation damage behaviors for titanium.