• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2011년도 춘계학술대회 논문집
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• pp.1309-1310
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• 2011

• Nuclear Engineering and Technology
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• 제49권7호
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• pp.1472-1482
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• 2017

Zirconium alloy cladding tube specimens were irradiated at $380^{\circ}C$ up to a fast neutron fluence of $7.5{\times}10^{24}n/m^2$ in a research reactor to investigate the effect of neutron irradiation on hydride reorientation and mechanical property degradation. Cool-down tests from $400^{\circ}C$ to $200^{\circ}C$ under 150 MPa tensile hoop stress were performed. These tests indicate that the irradiated specimens generated a smaller radial hydride fraction than did the unirradiated specimens and that higher hydrogen content generated a smaller radial hydride fraction. The irradiated specimens of 500 ppm-H showed smaller ultimate tensile strength and plastic strain than those characteristics of the 250 ppm-H specimens. This mechanical property degradation caused by neutron irradiation can be explained by tensile hoop stress-induced microcrack formation on the hydrides in the irradiation-damaged matrix and subsequent microcrack propagation along the hydrides and/or through the matrix.

• Structural Engineering and Mechanics
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• 제16권1호
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• pp.47-62
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• 2003

The nonlinear dependence aspect of various conical tool indentation parameters leading to an optimum tool semi angle value for easiest perforation is plotted and discussed explicitly in this work with the conclusion that tool angle has an optimum response towards most of the indentation parameters. Around this optimum angle, the aluminium sheets showed minimum fracture toughness as well as minimum work input to overcome the offered resistance. At the end, the mechanism leading to this phenomenon is presented with the conclusion that plastic flow dominates as the dimple semi cone angle reaches 35 and both pre and post plastic flow perforations lead the tool semi cone angle value towards this dimple cone semi angle of plastic flow initiation for its optimum performance. It is also concluded that specimen material failure is solely under tensile hoop stress and hence results into radial cracks initiation and propagation.

• Nuclear Engineering and Technology
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• 제50권2호
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• pp.306-312
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• 2018

There is an increasing need in the United States and around the world to move used nuclear fuel from wet storage in fuel pools to dry storage in casks stored at independent spent fuel storage installations or interim storage sites. Under normal conditions, the Nuclear Regulatory Commission limits cladding temperature to $400^{\circ}C$ for high-burnup (>45 GWd/mtU) fuel, with higher temperatures allowed for low-burnup fuel. An analysis was conducted with FRAPCON-4.0 on three modern fuel designs with three representative used nuclear fuel storage temperature profiles that peaked at $400^{\circ}C$. Results were representative of the majority of US light water reactor fuel. They conservatively showed that hoop stress remains below 90 MPa at the licensing temperature limit. Results also show that the limiting case for hoop stress may not be at the highest rod internal pressure in all cases but will be related to the axial temperature and oxidation profiles of the rods at the end of life and in storage.

• Structural Engineering and Mechanics
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• 제61권6호
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• pp.747-754
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• 2017

Exact solutions for stresses for an infinite rectangular plate perforated by two circular holes of different radii subjected to uni-axial or bi-axial uniform loads are investigated using the Airy stress function. The hoop stresses occurring at the edge of the circular hole are computed and plotted. Comparisons are made for the stress concentration factors for several types of loading conditions.

• 에너지공학
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• 제28권3호
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• pp.1-9
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• 2019

화력발전소에서 사용되는 급수 가열기 튜브에서는 사용중에 두께 감육이 발생하여 수명이 소진된다. 감육에 의한 파열 우려가 있으면 수명이 종료되는데, 파열조건을 결정하는 튜브 벽의 응력은 내압에 의한 원주방향 응력의 영향이 가장 큰 것으로 알려져 있지만, 튜브 내외부 온도차이에 의한 열응력에 대한 고려 또한 필요하다. 튜브 두께 방향의 온도차이는 열응력을 발생시켜 튜브의 잔여수명을 단축시키는 영향을 준다. 본 논문에서는 급수가열기 내에서 튜브 내표면과 외표면에 온도 차이가 가장 큰 과열저감구역(de-superheating zone)을 대상으로 열응력을 연구하였다. 원주방향으로 균일하게 감육된 튜브에서 두께방향의 온도차 때문에 발생하는 원주방향 응력, 반경방향 응력 및 온도분포를 평가하기 위한 해석적 수식을 제시하였다. 제시된 해석식의 정확도와 효과를 검증하기 위해 식으로부터의 계산된 결과를 유한요소해석으로 평가한 정확한 결과와 비교하였다. 또한, 유한요소해석으로 편심 감육된 튜브에 대한 응력도 평가하였다. 열응력 해석 및 온도 분포 해석에서 대류열전달 계수의 영향을 분석하기 위해 튜브 내표면 및 외표면에 여러 값의 열대류 계수를 적용하여 해석 결과를 비교하였다. 해석 결과 튜브 내표면보다 외표면의 열대류 계수가 응력 발생에 더 큰 영향을 주는 것으로 나타났다. 열하중만 고려된 경우, 균일 감육과 편심 감육 상태 모두에서 원주방향 응력이 반경방향 응력보다 크게 평가되었다.

• Journal of Mechanical Science and Technology
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• 제20권11호
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• pp.1920-1933
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• 2006

Piezoelectric materials produce an electric field by deformation, and deform when subjected to an electric field. The coupling nature of piezoelectric materials has acquired wide applications in electric-mechanical and electric devices, including electric-mechanical actuators, sensors and structures. In this paper, a hollow sphere composed of a radially polarized spherically anisotropic piezoelectric material, e.g., PZT_5 or (Pb) (CoW) $TiO_3$ under internal or external uniform pressure and a constant potential difference between its inner and outer surfaces or combination of these loadings has been studied. Electrodes attached to the inner and outer surfaces of the sphere induce the potential difference. The governing equilibrium equations in radially polarized form are shown to reduce to a coupled system of second-order ordinary differential equations for the radial displacement and electric potential field. These differential equations are solved analytically for seven different sets of boundary conditions. The stress and the electric potential distributions in the sphere are discussed in detail for two piezoceramics, namely PZT _5 and (Pb) (CoW) $TiO_3$. It is shown that the hoop stresses in hollow sphere composed of these materials can be made virtually uniform across the thickness of the sphere by applying an appropriate set of boundary conditions.

• 항공우주시스템공학회지
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• 제12권1호
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• pp.47-56
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• 2018

본 논문에서는 정지궤도복합위성 추진계 배관망의 독자적인 구조해석을 실시하였고, AIRBUS의 구조해석결과와 비교분석을 통해 추진계 배관망의 구조적 건전성 및 해석방법의 신뢰성을 평가하였다. 추진계 배관망의 구조적 신뢰성 확보는 정지궤도복합위성 추진계의 매우 중요한 핵심요소이다. 따라서 CAE 프로그램을 통해 직접 추진계 배관망 모델링을 수행하였고, 발사환경에서 구조해석을 실시하여 응력을 도출하였다. 내압응력해석, 조립정렬해석, 정현파진동해석, 랜덤진동해석의 하중조건에 따라 Hoop stress, Axial stress, Bending stress, Torsion stress를 구하였고, 이를 모두 고려한 von Mises 응력 계산 후 안전여유 결과 값을 도출함으로써 추진계 배관망의 구조적 건전성을 판단하였다.

• Nuclear Engineering and Technology
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• 제46권5호
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• pp.681-688
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• 2014

Hydride reorientation behaviors of PWR cladding tubes under typical interim dry storage conditions were investigated with the use of as-received 250 and 485ppm hydrogen-charged Zr-Nb alloy cladding tubes. In order to evaluate the effect of typical cool-down processes on the radial hydride precipitation, two terminal heat-up temperatures of 300 and $400^{\circ}C$, as well as two terminal cool-down temperatures of 200 and $300^{\circ}C$, were considered. In addition, two cooling rates of 2.5 and $8.0^{\circ}C/min$ during the cool-down processes were taken into account along with zero stress or a tensile hoop stress of 150MPa. It was found that the 250ppm hydrogen-charged specimen experiencing the higher terminal heat-up temperature and the lower terminal cool-down temperature generated the highest number of radial hydrides during the cool-down process under 150MPa hoop tensile stress, which may be explained by terminal solid hydrogen solubilities for precipitation, and dissolution and remaining circumferential hydrides at the terminal heat-up temperatures. In addition, the slower cool-down rate generates the larger number of radial hydrides due to a cooling rate-dependent, longer residence time at a relatively high temperature that can accelerate the radial hydride nucleation and growth.

• 한국표면공학회지
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• 제30권3호
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• pp.191-201
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• 1997

Non-passivated electrolytic tinplates withour conventinal chemical treatment self-oxidize in ambient atmosphere to from yellow stain on the outermost surface during the long-term storage. The degree of yellowness of the stain increased linerly with the oxide thickness due to the interfeefence color of the $SnO_2$ Even though the thickness of the oxide layer was very thin, less than 100$\AA$ , it exerts an undesirable influence on the can-making processes, particularly the stripping behavior after ironing. Investigations were carried out on the morphologies of the coating layer, the changes in oxide thickness during successive can-making processes and the averge friction coefficients with the different oxide thinkness. These oxide layers were broken up and distributed within the bulk tin coating during the ironing process. This redistribution of the oxide layer prvented smooth pressing-aside of the tin coating layer, resulting in an increase in the ironing friction coefficient. As the friction was increased, the residual stress along the can wall thinkness(i.e., the hoop stress) was also increased. Due to both the oxibe layer accumulation, which increased the friction coefficient, and the hoop stress, can stripping efficiency without roll-back is reduced.