• 한국공간구조학회논문집
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• 제10권1호
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• pp.51-58
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• 2010

ETFE 필름 막재는 Ethylen Tetra Fluoro Etylene의 약자로, 무색의 투명한 막재료이다. ETFE 필름 막재는 내화학성이 있고 매우 가벼운 장점이 있는 것으로 알려져 있다. ETFE 필름 막재는 $50{\mu}m$에서 $300{\mu}m$의 두께가 주로 사용되며, 인장강도는 40MPa에서 60MPa 300%에서 400%정도이다. 본 연구에서는 최근 해외에서 초대형 박구조물의 박재료로 시용되는 ETFE 필름 막재에 대한 기초적 역학적 특성을 조사하기 위하여 인장시험을 수행하였다. 인장시험으로부터 인장강도, 인장연신율, 영계수(Young's Modulus) 등 건축 설계 시 필요한 기초적 자료를 제공하고자 한다.

• Nuclear Engineering and Technology
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• 제45권5호
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• pp.581-588
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• 2013

This paper deals with the Safety Analysis for $CANDU^{(R)}$ 6 nuclear reactors as affected by main Heat Transport System (HTS) aging. Operational and aging related changes of the HTS throughout its lifetime may lead to restrictions in certain safety system settings and hence some restriction in performance under certain conditions. A step in confirming safe reactor operation is the tracking of relevant data and their corresponding interpretation by the use of appropriate thermal-hydraulic analytic models. Safety analyses ranging from the assessment of safety limits associated with the prevention of intermittent fuel sheath dryout for a slow Loss of Regulation (LOR) analysis and fission gas release after a fuel failure are summarized. Specifically for fission gas release, the thermal-hydraulic analysis for a fresh core and an 11 Effective Full Power Years (EFPY) aged core was summarized, leading to the most severe stagnation break sizes for the inlet feeder break and the channel failure time. Associated coolant conditions provide the input data for fuel analyses. Based on the thermal-hydraulic data, the fission product inventory under normal operating conditions may be calculated for both fresh and aged cores, and the fission gas release may be evaluated during the transient. This analysis plays a major role in determining possible radiation doses to the public after postulated accidents have occurred.

• Nuclear Engineering and Technology
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• 제44권6호
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• pp.561-586
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• 2012

This paper describes a summary of final prediction results by system-scale safety analysis codes during the OECD/NEA/CSNI ISP-50 exercise, targeting a 50% Direct Vessel Injection (DVI) line break integral effect test performed with the Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS). This ISP-50 exercise has been performed in two consecutive phases: "blind" and "open" phases. Quantitative comparisons were performed using the Fast Fourier Transform Based Method (FFTBM) to compare the overall accuracy of the collected calculations. Great user effects resulting from the combination of the possible reasons were found in the blind phase, confirming that user effect is still one of the major issues in connection with the system thermal-hydraulic code application. Open calculations showed better prediction accuracy than the blind calculations in terms of average amplitude (AA) value. A total of nineteen organizations from eleven countries participated in this ISP-50 program and eight leading thermal-hydraulic system analysis codes were used: APROS, ATHLET, CATHARE, KORSAR, MARS-KS, RELAP5/MOD3.3, TECH-M-97, and TRACE.

• Child Studies in Asia-Pacific Contexts
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• 제3권1호
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• pp.13-31
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• 2013

The children of sex workers in Bangladesh are denied even the most basic human rights. This article is based on recent research focused on the children of sex workers in the context of their everyday lives. The study focused on access to education and how education could be a vehicle for them to break the vicious cycle of exploitation. This was a mixed method interpretative study which employed qualitative and quantitative approaches, but in this paper only qualitative data which was generated through in-depth interviews and focus group discussions is used. Data was collected from sex workers, their children, teachers and NGO workers who participated in the study. Information has been collected for analysing the expectation of the children of sex workers and hope for the future, and the opportunities available to them during their schooling. Thematic analysis technique was used to understand the challenges and barriers faced by the children of sex workers in fulfilling their educational aspirations. The lives of the children of sex workers are marginalised by the mainstream society. Though it is very difficult to break the vicious cycle of exploitation, this research finds that education may be a stepping stone for them to create a better future. However, it is argued that the children of sex workers need income generating vocational and technical education to enable them to earn and support their family. Policy recommendations have been made in order to achieve Education For All targets and Millennium Development Goals, and to provide a second chance for these vulnerable young people to have a better life.

• 한국지능시스템학회논문지
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• 제20권5호
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• pp.728-733
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• 2010

대규모 DC 전력시스템에서는 회로차단기와 계전기로 대표되는 기존의 전자기적 회로 차단기가 산업 전 분야에 널리 이용되고 있다. 최근에는 고 신뢰성, 원격제어능력, 과부화와 단락전류 보호, 적은 열손실 등의 장점을 가지고 있는 원격전력제어기를 MOSFET 반도체 스위칭 소자를 이용하여 개발하고 있는 추세이다. 따라서 원격전력제어기는 고품질을 요구하는 시스템에서 필수적인 부품이 되어가고 있다. 본 논문에서는 원격전력제어장치를 모델링하였고 DSP를 이용하여 과전류 여부를 미리 판단할 수 있는 테스트 환경을 구현하여 최적 신호범위를 산출하였다.

• Nuclear Engineering and Technology
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• 제45권3호
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• pp.347-360
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• 2013

This paper presents an experimental investigation of the small-break loss-of-coolant accident (SBLOCA) and the loss-of-feedwater accident (LOFW) in a scaled integral test facility of REX-10. REX-10 is a small integral-type PWR in which the coolant flow is driven by natural circulation, and the RCS is pressurized by the steam-gas pressurizer. The postulated accidents of REX-10 include the system depressurization initiated by the break of a nitrogen injection line connected to the steam-gas pressurizer and the complete loss of normal feedwater flow by the malfunction of control systems. The integral effect tests on SBLOCA and LOFW are conducted at the REX-10 Test Facility (RTF), a full-height full-pressure facility with reduced power by 1/50. The SBLOCA experiment is initiated by opening a flow passage out of the pressurizer vessel, and the LOFW experiment begins with the termination of the feedwater supply into the helical-coil steam generator. The experimental results reveal that the RTF can assure sufficient cooldown capability with the simulated PRHRS flow during these DBAs. In particular, the RTF exhibits faster pressurization during the LOFW test when employing the steam-gas pressurizer than the steam pressurizer. This experimental study can provide unique data to validate the thermal-hydraulic analysis code for REX-10.

• 대한기계학회논문집A
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• 제28권4호
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• pp.352-361
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• 2004

One important element of the Leak-Before-Break analysis of nuclear piping is how to determine relevant fracture toughness (or the J-resistance curve) for nonlinear fracture mechanics analysis. The practice to use fracture toughness from a standard C(T) specimen is known to often give conservative estimates of toughness. To improve the accuracy, this paper proposes a new method to determine fracture toughness using a nonstandard testing specimen, curved wide-plate in tension. To show validity of the proposed curved wide-plate test, the J-resistance curve from the full-scale pipe test is compared with that from the curved wide-plate test and that from the C(T) specimen. It is shown that the J-resistance curve form the curved wide-plate tension test is similar to, but that from the C(T) specimen is lower than, the J-resistance curve from the full-scale pipe test. Further validation is performed by investigating crack-tip constraint conditions via detailed 3-D FE analyses, which shows that the crack-tip constraint condition in the curved wide-plate tension specimen is indeed similar to that in the full-scale pipe under bending.

• 한국정밀공학회지
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• 제16권3호통권96호
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• pp.30-37
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• 1999

This paper represents the development of the brake system for the inline skate using bellows. The inline skate that is used at present has defects due to frequent impulse, which weakens the breaking force by damaging the parts. Therefore to solve these problems a break system for the inline skates using hydraulics is suggested. To solve the oil leakage problems, bellows is used. Also to prevent the breaks from not touching the ground when skating the bellows is placed at the heel, high as possible. To obtain fast response speed, the ratio of inner diameter of the bellows is changed so that with only a small displacement from the bellows the rubber pad attached to the bellows will touch the ground fast. The performance of the break system using bellows depends on the optimal design of the bellows. Therefore the parameters that changes the form of the bellows are tested and also the interaction between the forces are investigated. The performance of new model brake system with bellows and old model system with only a rubber pad without bellows was estimated through observation of braking posture.

• Nuclear Engineering and Technology
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• 제36권5호
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• pp.475-484
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• 2004

Extending the lifetime of a nuclear power plant [(hereafter referred to simply as NPP)] is one of the most important concerns in the global nuclear industry. Cables are one of the long-life items that have not been considered for replacement during the design life of a NPP. To extend the cable life beyond the design life, it is first necessary to prove that the design life is too conservative compared with actual aging. Condition monitoring is useful means of evaluating the aging condition of cable. In order to simulate natural aging in a nuclear power plant. a study on accelerated aging must first be conducted. In this paper, evaluations of mechanical aging degradation for a neoprene cable jacket were performed after accelerated aging under tcontinuous and intermittent heating conditions. Contrary to general expectations, intermittent heating to the neoprene cable jacket showed low aging degradation, 50% break-elongation, and 60% indenter modulus, compared with continuous heating. With a plant maintenance period of 1 month after every 12 or 18 months operation, we can easily deduce that the life time of the cable jacket of neoprene can be extended much longer than extimated through the general EQ test. which adopts continuous accelerated aging for determining cable life. Therefore, a systematic approach that considers the actual environment conditions of the nuclear power plant is required for determining cable life.

• 화약ㆍ발파
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• 제39권3호
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• pp.44-64
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• 2021

4차 산업혁명 시대의 도래와 함께 빅데이터의 활용과 인공지능 기법을 활용한 공학적 응용이 증가하고 있다. 발파 분야에서도 인공지능 기법을 활용한 다양한 연구들이 보고되고 있다. 본 논문에서는 발파분야에서 많이 활용되고 있는 인공신경망, 퍼지 이론, 유전자 알고리즘, 떼 지능, 서포트 벡터머신과 같은 인공지능 기법을 소개하고 이들 기법을 이용한 발파진동, 비석, 암석 파쇄도, 폭풍압, 여굴 예측 기법에 대한 연구들을 조사, 정리하였다. 향후 인공지능 기법을 활용하여 보다 효율적이고 안전한 발파설계, 발파 효율 향상과 발파에 의한 주변 환경에 미치는 영향을 최소화하기 위하기 위한 발전적인 접근 방향에 대한 논의에 활용할 수 있는 기초 자료를 제공하고자 한다.