• 인터넷정보학회논문지
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• 제12권2호
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• pp.75-83
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• 2011

무선 인지(CR : Cognitive Radio) 시스템은 우선 사용자에게 할당되어 있지만 실제로 사용되지 않는 주파수 대역을 감지하고 사용함으로써 스펙트럼 효율을 향상시킬 수 있는 기술이다. 우선 사용자가 채널을 점유하게 되면 무선 인지 시스템은 우선사용자 시스템에 대한 간섭을 피하기 위해 다른 채널로 이동해야 하며, 이 때 새로운 채널에서 무선 인지 시스템 송 수신기가 핸드셰이크를 하기 까지 통신 단절 시간이 생기게 된다. 따라서 무선 인지 시스템에 대한 서비스 품질의 보장을 위해서는 보다 빠른 핸드셰이크 기법이 요구된다. 본 논문에서는 Broadcasting 구간뿐만 아니라 데이터 전송 구간에서도 임베디드 제어 신호를 전송함으로써 무선 인지 시스템의 통신단절시간을 감소시키고, 데이터 전송률을 높일 수 있는 기법을 제안한다. 마지막으로 컴퓨터 모의실험 결과를 통해 제안하는 임베디드 제어 신호 전송 방식이 기존의 방식보다 우수한 성능을 보임을 확인하였다.

• 한국수자원학회:학술대회논문집
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• 한국수자원학회 2008년도 학술발표회 논문집
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• pp.1752-1756
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• 2008

A simple, accurate and efficient mesh generation technique, the cut-cell method, is able to represent an arbitrarily complex geometry. Both structured and unstructured grid meshes are used in this method. First, the numerical domain is constructed with regular Cartesian grids as a background grid and then the solid boundaries or bodies are cut out of the background Cartesian grids. As a result, some boundary cells can be contained two numerical conditions such as the flow and solid conditions, where the special treatment is needed to simulate such physical characteristics. The HLLC approximate Riemann solver, a Godunov-type finite volume method, is employed to discretize the advection terms in the governing equations. Also, the TVD-WAF method is applied on the Cartesian cut-cell grids to stabilize numerical results. Present method is validated for the rectangular dam break problems. Initially, a conventional grid is constructed with the Cartesian regular mesh only and then applied to the dam-break flow simulation. As a comparative simulation, a cut-cell grids are applied to represent the flow domain rotated with arbitrary angles. Numerical results from this study are compared with the results from the case of the Cartesian regular mesh only. A good agreement is achieved with other numerical results presented in the literature.

• Journal of Biosystems Engineering
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• 제16권3호
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• pp.211-218
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• 1991

In this study, the break of the rotary blade which is occured from a stress concentration of the inside of blade by the outside impulsive load, is analyzed to 3-dimension used by the Freezing Photoelastic Method. These results are as follows. 1. The bending and compression stress are the greatest at the location of blade case. 2. The section area of 3cm-location from the blade case is the smallest, therefore, there are breaked 58% of all at this location and are proofed to the most danger section 3. The section area which by stress concentration of 3cm-location from blade case is caused by the production of blade, and it was higher danger of break than another location's. 4. In the location of 6cm and 9cm from the blade case, the bending stress has received a little and the section area has larger than another's, so it is not almost possible that the break at that location 5. In order to prevent of break, the external part which has contacted soil have to made tender for receiving a little stress and the internal part which received a large stress have to strengthen.

• 한국압력기기공학회 논문집
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• 제7권3호
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• pp.40-47
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• 2011

KSNPs(Korea Standard Nuclear Power Plant) have been applied the break exclusion criteria to the high energy lines passing through containment penetration area to ensure that piping failures would not cause the loss of containment isolation function, and to reduce the resulting dynamic effects. Systems with the criteria are the Main Steam system, Feed Water system, Steam Generator Blowdown system, and Chemical & Volume Control system. In accordance with FSAR(Final Safety Analysis Report), a 100% volumetric examination by augmented in-service inspection of all pipe welds appled the break exclusion criteria is required for the break exclusion application piping. However, it is difficult to fully satisfy the requirements of inspection because 12", 8" and 6" weldolet weldments of Main Steam pipe line have complex structural shapes. To resolve the difficulty on the application of conventional UT(Ultrasonic Testing) technique, realistic mock-ups and UT calibration blocks were made. Simulations of conventional UT were performed utilizing CIVA, a commercial NDE(Nondestructive Examination) simulation software. Phased array UT experiments were performed through mock-up including artificial notch type flaws. A phased array UT technique is finally developed to improve the reliability of ultrasonic test at main steam line pipe to 12", 8" and 6" branch connection weld.

• 한국압력기기공학회 논문집
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• 제13권1호
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• pp.54-60
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• 2017

When a sudden rupture occurs in high energy lines, ejection of inner fluid with high temperature and pressure causes blast wave as well as thrust forces on the ruptured pipe itself. The present study is to examine pipe whip behaviors and blast wave phenomena under postulated pipe break conditions. In this context, typical numerical models were generated by taking a MSL (Main Steam Line) piping, a steam generator and containment building. Subsequently, numerical analyses were carried out by changing break locations; one is pipe whip analyses to assess displacements and stresses of the broken pipe due to the thrust force. The other is blast wave analyses to evaluate the broken pipe due to the blast wave by considering the pipe whip. As a result, the stress value of the steam generator increased by about 7~21% and von Mises stress of steam generator outlet nozzle exceeded the yield strength of the material. In the displacement results, rapid movement of pipe occurred at 0.1 sec due to the blast wave, and the maximum displacement increased by about 2~9%.

• 한국수정란이식학회지
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• 제30권3호
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• pp.189-193
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• 2015

Calculating break-even price of calf production is closely associated with reproductive efficiency. To determine the price, we need data from reproduction records including number of claves weaned, number of cows exposed for breeding, and annual cash coast per cow, and average weaning or market weight of claves sold and retained. Unfortunately, the data were not available in Korea native cow (Hanwoo). To evaluate the performance and the price, we collected calving interval from about 60,000 cows for last 10 years and estimated reproductive performance. Calving interval was increased 4.3% and pregnancy rate was decreased about 1.4~2.8% year-on-year. Increases in growth rates of number of cow and semen per calf supported the low reproductive performance. Finally, break-even price was calculated using estimated percent calf crop and demonstrated that growth rate of break-even price is larger than that of annual cash per cow, suggesting cow-calf profitability and financial efficiency in Korea native cow (Hanwoo) is getting worse.

• Elastomers and Composites
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• 제56권3호
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• pp.124-135
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• 2021

Evaluating service lives of rubber materials at certain temperatures requires a destructive method (typically using elongation at break). In this study, a non-destructive method based on hardness change rate was proposed for evaluating the service life of chloroprene rubber (CR). Compared to the destructive method, this non-destructive method ensures homogeneity of CR specimens and requires a small number of samples. Thermal accelerated degradation test was conducted on the CR specimens at 55, 70, 85, 100, and 125℃, and the tensile strength, elongation at break, and hardness were measured. The results of the experiment were compared to those of the accelerated life evaluation method proposed in this study. Comparing the analyzed lives in the high temperature region (70, 85, 100, and 125℃), the difference between the service lives for the destructive method (using the elongation at break) and non-destructive method (using the hardness) was approximately 0.1 year. Therefore, it was confirmed that the proposed non-destructive evaluation method based on hardness changes can evaluate the actual life of CR under thermally accelerated degradation conditions.

• KEPCO Journal on Electric Power and Energy
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• 제5권1호
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• pp.11-15
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• 2019

최근 송전전압 격상으로 인해 차단기 또한 정격이 높아지고 있다. 이에 차단부의 전압 정격을 높이기 위한 방법으로 차단부 2개 이상을 직렬로 구성하는 다점절 차단기가 설치되어 운용되고 있다. 다점절 차단기에서 차단부 극간에 설치되는 균압용 콘덴서는 점절간 균등한 전압분배와 초기 과도회복전압을 저감하는 기능을 수행한다. 하지만, 세계적으로 실계통 사용에서 균압용 콘덴서는 기계적인 손상, 절연파괴에 의한 폭발 등 다수의 고장이 발생하고 있어, 이에 대한 원인 규명과 새로운 성능 검증방법에 대한 연구 필요성이 제기 되고 있다. 본 논문에서는 한전 계통에서 주로 발생한 균압용 콘덴서의 절연파괴 원인을 규명하고 이에 대한 제품 성능검증 방법을 제안하고자 한다.

• 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.

• Nuclear Engineering and Technology
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• 제55권7호
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• pp.2438-2446
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• 2023

To cool down a nuclear reactor core and prevent the fuel damage without a pump-driven active component during any anticipated accident, the passive emergency core cooling system (PECCS) was designed and adopted in an advanced light water reactor, i-POWER. In this study, for a validation of the cooling capability of PECCS, thermal-hydraulic integral effect tests were performed with the ATLAS facility by simulating intermediate and small break loss-of-coolant accidents (IBLOCA and SBLOCA). The test result showed that PECCS could effectively depressurize the reactor coolant system by supplying the safety injection water from the safety injection tanks (SITs). The result pointed out that the safety injection from IRWST should have been activated earlier to inhibit the excessive core heat-up. The sequence of the PECCS injection and the major thermal hydraulic transient during the SBLOCA transient was similar to the result of the IBLOCA test with the equivalent PECCS condition. The test data can be used to evaluate the capability of thermal hydraulic safety analysis codes in predicting IBLOCA and SBLOCA transients under an operation of passive safety system.