• 제목/요약/키워드: Rupture energy

검색결과 218건 처리시간 0.026초

ONO Ruptures Caused by ONO Implantation in a SONOS Non-Volatile Memory Device

  • Kim, Sang-Yong;Kim, Il-Soo
    • Transactions on Electrical and Electronic Materials
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    • 제12권1호
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    • pp.16-19
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    • 2011
  • The oxide-nitride-oxide (ONO) deposition process was added to the beginning of a 0.25 ${\mu}m$ embedded polysiliconoxide-nitride-oxide-silicon (SONOS) process before all of the logic well implantation processes in order to maintain the characteristics of basic CMOS(complementary metal-oxide semiconductor) logic technology. The system subsequently suffered severe ONO rupture failure. The damage was caused by the ONO implantation and was responsible for the ONO rupture failure in the embedded SONOS process. Furthermore, based on the experimental results as well as an implanted ion's energy loss model, processes primarily producing permanent displacement damages responsible for the ONO rupture failure were investigated for the embedded SONOS process.

Al 7075 합금의 크리이프 파단수명에 관한 연구(II) (A Study on the Creep Fracture Life of Al 7075 Alloy(II))

  • 강대민
    • 한국안전학회지
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    • 제9권4호
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    • pp.29-41
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    • 1994
  • High temperature tensiles tests, steady state creep tests, internal stress tests and creep rupture tests using Al 7075 alloy were performed over the temperature range of 9$0^{\circ}C$~50$0^{\circ}C$ and stress range of 0.64~17.2(kgf/$\textrm{mm}^2$) in order to investigate the creep behavior and predict creep rupture life From the apparent activation energy Qc and the applied stress exponent n measured, at the temperature range of 9$0^{\circ}C$~l2$0^{\circ}C$, the creep deformation seemed to be controlled by cross slip. On the other hand at the temperature of 20$0^{\circ}C$~23$0^{\circ}C$ the creep deformation seemed to be controlled by dislocation climb but at 47$0^{\circ}C$~50$0^{\circ}C$, by diffusion creep. And the rupture life(t$_{f}$) might be represented by anthermal process attributed to the difference of the applied stress dependence of Internal stress and the ratio of the Internal stress to the applied stress, the thermal activated process attributied to the temperature dependence of the internal stress. Also the ratio between stress dependence of primary creep rate and that of minimum creep rate was measured 0.46, the minimum creep rate is expected to be appromately obtained from master creep curve including the relationship primary creep rate and minumum creep rate. Finally the relationship new rupture parameter and logarithmic stress was represented with including the ratio between the dependence of primary creep rate and that of minimum creep rate, using the new rupture parameter the rupture life predition is exactly expected.d.

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축구 경기 중 발생한 장골근 파열과 부분 대퇴 신경 마비 - 증례보고 - (Iliacus Muscle Rupture with Associated Partial Femoral Nerve Palsy during Soccer Game - Case Report -)

  • 정성훈;이상호;송경섭;박병문;기철현
    • 대한정형외과스포츠의학회지
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    • 제11권2호
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    • pp.92-95
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    • 2012
  • 장골근 파열은 매우 드물게 발생하는 손상으로 고에너지 외상이나 혈액 응고 기능 장애, 항혈액응고제 사용자, 혈우병 환자 등 출혈경향이 있는 환자에서 저에너지 손상을 받는 경우에 발생할 수 있다. 장골근의 파열로 인한 혈종의 압박에 의해 발생한 대퇴 신경 마비가 국내에도 드물게 보고된 바가 있다. 자기공명영상 검사로 병변 부위를 확진하고 신경전도 검사 및 근전도 검사로 대퇴신경 마비의 범위를 평가할 수 있고 혈액응고 기능에 문제가 있거나 출혈경향이 있는 환자를 선별하기 위해 반드시 혈액학적인 검사가 선행되어야 한다. 저자들은 정상적인 32세 남자가 축구 경기 도중 공을 차는 동작에서 발생한 장골근 파열 및 혈종의 압박으로 인한 부분적인 대퇴신경 마비의 증례를 경험하고 6개월간 추시 관찰하였으며, 양호한 결과를 얻었기에 문헌고찰과 함께 보고하는 바이다.

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Large Steel Tank Fails and Rockets to Height of 30 meters - Rupture Disc Installed Incorrectly

  • Hedlund, Frank H.;Selig, Robert S.;Kragh, Eva K.
    • Safety and Health at Work
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    • 제7권2호
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    • pp.130-137
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    • 2016
  • At a brewery, the base plate-to-shell weld seam of a $90-m^3$ vertical cylindrical steel tank failed catastrophically. The 4 ton tank "took off" like a rocket leaving its contents behind, and landed on a van, crushing it. The top of the tank reached a height of 30 m. The internal overpressure responsible for the failure was an estimated 60 kPa. A rupture disc rated at < 50 kPa provided overpressure protection and thus prevented the tank from being covered by the European Pressure Equipment Directive. This safeguard failed and it was later discovered that the rupture disc had been installed upside down. The organizational root cause of this incident may be a fundamental lack of appreciation of the hazards of large volumes of low-pressure compressed air or gas. A contributing factor may be that the standard piping and instrumentation diagram (P&ID) symbol for a rupture disc may confuse and lead to incorrect installation. Compressed air systems are ubiquitous. The medium is not toxic or flammable. Such systems however, when operated at "slight overpressure" can store a great deal of energy and thus constitute a hazard that ought to be addressed by safety managers.

An Empirical Approach to Analyze Creep Rupture Behavior of P91 Steel

  • Aslam, Muhammad Junaid;Gur, Cemil Hakan
    • 한국재료학회지
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    • 제31권5호
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    • pp.255-263
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    • 2021
  • P91 steel has been a highly researched material because of its applicability for high-temperature applications. Considerable efforts have been made to produce experimental creep data and develop models for creep life prediction. As creep tests are expensive and difficult to conduct, it is vital to develop authenticated empirical methods from experimental results that can be utilized for better understanding of creep behavior and can be incorporated into computational models for reliable prediction of creep life. In this research, a series of creep rupture tests are performed on the P91 specimens within a stress range of 155 MPa to 200 MPa and temperature range of 640 ℃ (913 K) to 675 ℃ (948 K). The microstructure, hardness, and fracture surfaces of the specimens are investigated. To analyze the results of the creep rupture tests at a macro level, a parameter called creep work density is derived. Then, the relationships between various creep parameters such as strain, strain rate, time to rupture, creep damage tolerance factor, and creep work density are investigated, and various empirical equations are obtained.

Al-Zn-Mg 3원계 알루미늄 합금의 크리프 거동 (Creep Behaviour of Al-Zn-Mg Ternary Aluminum Alloy)

  • 윤종호;황경충
    • 한국자동차공학회논문집
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    • 제12권1호
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    • pp.203-208
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    • 2004
  • To make practical applications of Al-Zn-Mg ternary aluminum alloy effectively in various field, a series of static creep tests under the 16 temperature-stress combination conditions had been performed. The creep tester with constant stress loading was designed and made by the authors and used in this study. The higher the creep temperature rose, the less the stress exponents became. The bigger the applied stresses became, the less values the creep strain activation energy showed. The life prediction constant of Larson-Miller parameter was calculated as about 2.3. In the fractography, the ductile fracture with dimples by intergranular breakage was primarily observed. We can make practical use of these test data in the design, the life prediction and the prevention of the accidents of the thermal facilities, etc.

액상 암모니아 충전 용기의 파열 원인 분석 (Investigation into the Causes of Rupturing Ammonia-filled Cylinders)

  • 전병일;박창협
    • 한국수소및신에너지학회논문집
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    • 제35권4호
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    • pp.451-459
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    • 2024
  • This paper quantitatively analyzes the causes of ammonia-filled- cylinder rupture based on Tait equation and the safety guidelines, focusing on liquid expansion, internal temperature, and overfilling. When there exists a safety volume, i.e., gas-occupied volume within the ammonia cylinder, the internal pressure due to temperature rise corresponds to the vapor pressure at that temperature, with an approximate circumferential stress increase of 1.43 MPa/℃. In the absence of the safety volume, the internal pressure due to temperature rise matches the pressure of the compressed liquid ammonia at that temperature, and the resulting circumferential stress gradient in the cylinder shell is approximately 55.94 MPa/℃.

PSA기법을 이용한 원자력시설의 핵심구역 파악 (Vital Area Identification of Nuclear Facilities by using PSA)

  • 이윤환;정우식;황미정;양준언
    • 한국안전학회지
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    • 제24권5호
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    • pp.63-68
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    • 2009
  • The urgent VAI method development is required since "The Act of Physical Protection and Radiological Emergency that is established in 2003" requires an evaluation of physical threats in nuclear facilities and an establishment of physical protection in Korea. The VAI methodology is developed to (1) make a sabotage model by reusing existing fire/flooding/pipe break PSA models, (2) calculate MCSs and TEPSs, (3) select the most cost-effective TEPS among many TEPSs, (4) determine the compartments in a selected TEPS as vital areas, and (5) provide protection measures to the vital areas. The developed VAI methodology contains four steps, (1) collecting the internal level 1 PSA model and information, (2) developing the fire/flood/pipe rupture model based on level 1 PSA model, (3) integrating the fire/flood/pipe rupture model into the sabotage model by JSTAR, and (4) calculating MCSs and TEPS. The VAT process is performed through the VIPEX that was developed in KAERI. This methodology serves as a guide to develop a sabotage model by using existing internal and external PSA models. When this methodology is used to identify the vital areas, it provides the most cost-effective method to save the VAI and physical protection costs.

Analysis of steam generator tube rupture accidents for the development of mitigation strategies

  • Bang, Jungjin;Choi, Gi Hyeon;Jerng, Dong-Wook;Bae, Sung-Won;Jang, Sunghyon;Ha, Sang Jun
    • Nuclear Engineering and Technology
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    • 제54권1호
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    • pp.152-161
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    • 2022
  • We analyzed mitigation strategies for steam generator tube rupture (SGTR) accidents using MARS code under both full-power and low-power and shutdown (LPSD) conditions. In general, there are two approaches to mitigating SGTR accidents: supplementing the reactor coolant inventory using safety injection systems and depressurizing the reactor coolant system (RCS) by cooling it down using the intact steam generator. These mitigation strategies were compared from the viewpoint of break flow from the ruptured steam generator tube, the core integrity, and the possibility of the main steam safety valves opening, which is associated with the potential release of radiation. The "cooldown strategy" is recommended for break flow control, whereas the "RCS make-up strategy" is better for RCS inventory control. Under full power, neither mitigation strategy made a significant difference except for on the break flow while, in LPSD modes, the RCS cooldown strategy resulted in lower break and discharge flows, and thus less radiation release. As a result, using the cooldown strategy for an SGTR under LPSD conditions is recommended. These results can be used as a fundamental guide for mitigation strategies for SGTR accidents according to the operational mode.

316L(N)스테인리스강의 Monkman-Grant 크리프 수명식의 적용성 (Application of Monkman-Grant Relationships to Type 316L(N) Stainless Steel)

  • 김우곤;김대환;류우석
    • 대한기계학회논문집A
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    • 제24권9호
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    • pp.2326-2333
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    • 2000
  • Creep tests for type 316L(N) stainless steel were carried out using constant-load creep machines at 55$0^{\circ}C$, 575$^{\circ}C$ and $600^{\circ}C$. Material constants necessary to predict creep rupture time were obtained from the experimental creep data. And the applicability of Monkman-Grant(M-G) and modified M-G relationships was discussed. The log-log plot of M-G relationship between the rupture time($t_r$,) and the minimum creep rate ($ $\varepsilon$ _m$) was dependent on test temperatures. The slope of m was 1,05 at 55$0^{\circ}C$ and m was 1.30 at $600^{\circ}C$. On the other hand, the log-log plot of modified M-G relationship between $t_r/$\varepsilon$_r$, and $ $\varepsilon$ _m$ was independent on stresses and temperatures. That is, the slope of m' was approximately 1.35 in all the data. Thus, modified M-G relationship for creep life prediction could be utilized more reasonably than that of M-G relationship for type 316L(N) stainless steel. It was analyzed that the constant slopes regardless of temperatures or applied stresses in the modified relationship were due to an intergranular fracture grown by wedge-type cavities.