• Investigative Magnetic Resonance Imaging
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• 제22권4호
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• pp.218-228
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• 2018

Purpose: The objective of this study is to determine the effect of physical changes on MR temperature imaging at 7.0T and to examine proton-resonance-frequency related changes of MR phase images and T1 related changes of MR magnitude images, which are obtained for MR thermometry at various magnetic field strengths. Materials and Methods: An MR-compatible capacitive-coupled radio-frequency hyperthermia system was implemented for heating a phantom and swine muscle tissue, which can be used for both 7.0T and 3.0T MRI. To determine the effect of flip angle correction on T1-based MR thermometry, proton resonance frequency, apparent T1, actual flip angle, and T1 images were obtained. For this purpose, three types of imaging sequences are used, namely, T1-weighted fast field echo with variable flip angle method, dual repetition time method, and variable flip angle method with radio-frequency field nonuniformity correction. Results: Signal-to-noise ratio of the proton resonance frequency shift-based temperature images obtained at 7.0T was five-fold higher than that at 3.0T. The T1 value increases with increasing temperature at both 3.0T and 7.0T. However, temperature measurement using apparent T1-based MR thermometry results in bias and error because B1 varies with temperature. After correcting for the effect of B1 changes, our experimental results confirmed that the calculated T1 increases with increasing temperature both at 3.0T and 7.0T. Conclusion: This study suggests that the temperature-induced flip angle variations need to be considered for accurate temperature measurements in T1-based MR thermometry.

• 한국압력기기공학회 논문집
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• 제8권1호
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• pp.25-32
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• 2012

Korea Hydro & Nuclear Power Co. (KHNP) has developed and implemented the maintenance effectiveness monitoring (MR) programs for the operating nuclear power plants. The MR program is developed by reflecting design characteristics of the operating nuclear power plants to monitor the plant performance for improving the safety and reliability. Recently, KHNP has built a new nuclear power plant, and developed the MR program to establish the advanced maintenance system by reflecting unique design characteristics based on the OPR1000 standard model. So, the MR program developed in this study has another characteristics in comparison with the OPR1000 standard model, and we will verify the suitability of the MR program through evaluating initial performance of the plant. The safety and reliability of the new plant will be improved by developing and implementing the MR program.

• 한국안전학회지
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• 제16권2호
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• pp.110-116
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• 2001

The objective of the Maintenance Rule (MR) is to require monitoring of the overall continuing effectiveness of licensee maintenance programs to ensure that the safety related and certain nonsafety-related SSCs are capable of performing their intended functions. In Korea, as risk informed applications and regulation become active, the necessity of Performance Based Regulation (PBR) has increased. The objective of this article is to study the effectiveness of MR based on performance and feasibility of MR adoption at Korean Nuclear Power Plants (NPPs) for effective maintenance and regulation.

• 한국기계가공학회지
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• 제8권1호
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• pp.57-63
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• 2009

Magneto-Rheological(MR) fluid composes of a base fluid and ferromagnetic particles less than tens of micrometer size dispersed in the fluid. It is called as a smart material because its rheological properties are changable by a magnetic field. Its important applications are active devices such as controllable dampers and controllable clutches. The merit of those products is that their functional characteristics are controllable such that they enable active control strategies. This paper proposes an idea for machine tool applications of the MR fluid clutch as a safety device for power transmission. FEM has been used for magnetic field analyses and the results are compared with some former experiments. Some design syntheses of the MR clutches are suggested and hopefully considered that it may be an effective safety device for power transmission of machine tools.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2003년도 춘계학술대회 논문집
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• pp.1063-1066
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• 2003

A flow-meter and its measurement controller was developed for a hydraulic system. This study, for development of positive displacement flow-meter, consist of PIC(Peripheral Interface Controller) controller with MR(Magneto-resistive) sensors. This flow-meter is used valve position indicator for valve control system by hydraulic. The MR sensors are used for the rotation of OVAL gear that detecting device. In the ship environments, consideration that necessary explosive proof. Thus electro device or electro flow-meter needs explosion design for electric circuit. We designed noncontact type flow-meter and evaluated the safety and measuring abilities.

• 한국안전학회지
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• 제27권6호
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• pp.14-19
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• 2012

The Helium cooled ceramic reflector(HCCR) test blanket module(TBM) has been designed and developed to participate the ITER(International Thermonuclear Experimental Reactor) test blanket program in Korea. The TBM was one of the main objectives for developing ITER for proving the tritium self-sufficiency and the heat transfers to produce the electricity with the breeding blanket concept. Among the TBM components, the first wall(FW) was the most important component in safety since it was directly faced a high level of a heat and fast neutrons from the plasma side and could protect the others components inside TBM. In this paper, the FW has been designed through the thermo-mechanical analysis considering ITER operation conditions. With the developed simple models, the stress limit analysis based on RCC-MR code which is the nuclear power plant design codes in France was evaluated for the allowable design criteria. The results showed that the designed FW model satisfied $1.5S_m$ or $3S_m$ of the allowable stress($S_m$) in RCC-MR code at the maximum stress region in the FW.

• 대한방사선기술학회지:방사선기술과학
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• 제44권2호
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• pp.123-131
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• 2021

In this study, safety education contents for medical radiation workers were produced based on Mixed Reality(MR). Currently, safety training for radiation workers is based on theory. This is insufficient in terms of worker satisfaction and efficiency. To address this, we created ICT(Information and Communication Technologies)-based MR radiation worker safety education content. The expected effect of Mixed Reality worker safety education content is that education is possible without space and time constraints, realistic education is possible without on-site training, and interaction between images is possible through reality-based 3D images, enabling self-directed learning Is that. In addition, learning in a virtual space expressed through HMD(Head Mounted Display) is expected to make education more enjoyable and increase concentration, thereby increasing the efficiency of education. A quantitative evaluation was conducted by an accredited institution and a qualitative evaluation was performed on users, which received excellent evaluation. The MR safety education conducted in this study is expected to be of great help to the education of medical radiation workers, and is expected to develop into a new educational paradigm as online education in accordance with Corona 19 progresses.

• 한국가스학회지
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• 제16권3호
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• pp.16-21
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• 2012

본 연구에서는 70MPa의 충전압력을 갖는 110L 수소연료 저장탱크에 대한 강도안전성을 FEM으로 해석하였다. 6061-T6 알루미늄 라이너의 외벽면에는 Toray의 T800-24K와 T700-12K, 그리고 Mitsubishi Ray의 MR60H-24P 탄소섬유를 사용하여 와인딩한 복합소재 연료탱크의 강도안전성을 미국의 DOT-CFFC와 KS의 안전규격으로 고찰하였다. 70MPa용 수소가스탱크의 응력강도에 대한 FEM 해석결과에 의하면, 거의 유사한 소재특성을 갖는 Toray의 T800-24K와 Mitsubishi Ray의 MR60H-24P는 70MPa의 수소연료 저장탱크를 제조하는데 사용해도 안전한 것으로 나타났다. 반면에, Toray의 T700-12K는 70MPa의 충전압력을 갖는 복합소재 저장탱크를 제조하기에는 강도안전성을 보장할 수 없으므로 60MPa 이하의 수소연료 복합소재탱크 제조를 권장한다.

• Korean Journal of Radiology
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• 제25권1호
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• pp.8-10
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• 2024

• 에너지공학
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• 제23권2호
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• pp.191-198
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• 2014

국내 가동중 원전은 발전소 안전성 및 신뢰성을 향상시킬 목적으로 정비효과감시 프로그램(정비규정)을 개발하여 2009년부터 이행 중에 있다. 정비효과감시 프로그램은 발전소 전 계통을 기능단위로 분류한 후 관리대상 선정, 안전중요도 결정 및 성능기준 수립을 통해 발전설비의 정비효과를 감시하는 프로그램이며, NUMARC 93-01 방법론을 기반으로 발전소별 고유 설계특성을 반영하여 개발하고 있다. 최근 건설 중인 APR1400형 원전도 운영초기 단계부터 정비체계 정착을 목적으로 안전관련계통 정비효과감시 프로그램을 개발하였으며, 향후 초기 성능평가를 통해 프로그램의 적합성을 검증할 예정이다. 결과적으로 고유 설계특성을 반영하여 개발한 정비효과감시 프로그램의 이행을 통해 APR1400형 원전의 안전성 및 신뢰성이 향상될 것으로 기대된다.