• 한국재료학회지
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• 제27권8호
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• pp.409-415
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• 2017

For enhanced cavitation erosion resistance of vessel propellers, an electroless Ni-P plating method was introduced to form a coating layer with high hardness on the surface of Cu alloy (CAC703C) used as vessel propeller material. An electroless Ni-P plating reaction generated by Fe atoms in the Cu alloy occurred, forming a uniform amorphous layer with P content of ~10 wt%. The amorphous layer transformed to (Ni3P+Ni) two phase structure after heat treatment. Cavitation erosion tests following the ASTM G-32 standard were carried out to relate the microstructural changes by heat treatment and the cavitation erosion resistance in distilled water and 3.5 wt% NaCl solutions. It was possible to obtain excellent cavitation erosion resistance through careful microstructural control of the coating layer, demonstrating that this electroless Ni-P plating process is a viable coating process for the enhancement of the cavitation erosion resistance of vessel propellers.

• Journal of Welding and Joining
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• 제33권2호
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• pp.40-46
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• 2015

This study was performed to investigate the effect of ultrasonic nano crystal surface modification (UNSM) on residual stress mitigation after Weld Inlay repair for butt dissimilar metal weld with Alloy 82/182 in reactor vessel In/Outlet nozzle. As-welded and Weld Inlay specimens were made in accordance with design standard of ASME Code Case N-766, and two planes of their weld specimens were peened by the optimum UNSM process condition. Peening characteristics for weld specimens after UNSM treatment were evaluated by surface roughness and Vickers hardness test. And, residual stress for weld specimens developed from before and after UNSM treatment was measured and evaluated by instrumented indentation technique. Consequently, it was revealed that the mitigation of residual stress in weld metal after Weld Inlay repair of reactor vessel In/Outlet nozzle could be possible through UNSM treatment.

• 한국압력기기공학회 논문집
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• 제9권1호
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• pp.20-24
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• 2013

Reactor Vessel Internals(RVIs), which are installed within the reactor pressure vessel and support the fuel assembly, take responsibility for safety of reactor core. In operating Nuclear Power Plants(NPPs), the RVIs have been exposed to severe conditions such as neutron irradiation, high temperature, high pressure, and high velocity of coolant flow and have degraded by materials aging with long-term operation. Therefore, the effective aging management plan and the appropriate regulatory requirements are necessary to maintain the integrity of RVIs. The purpose of this paper is to provide a review guide for Periodic Safety Review(PSR) of RVIs in presurized water reactor. The review guide is developed based on the revised review guides and reports established from IAEA and USNRC, and the analysis results of design characteristics, aging mechanisms, and operating experiences of RVIs in domestic and international NPPs. Consequently, the developed review guide for PSR of RVIs is expected to contribute an overall strategy and standard for the PSR of RVIs.

• 시스템엔지니어링학술지
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• 제13권1호
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• pp.15-23
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• 2017

This paper describes verification of APR1400 reactor vessel by applying the system engineering approach, in which the design re-engineering method is used to check the design parameters of APR1400 RV (reactor vessel). The RV is classified as safety class 1 and therefore must adhere strictly to the rules of ASME BPVC section III, subsection NB and seismic category I. This study explores designing the RV by following the ASME guidelines and making a comparative study with the current design. To meet this objective we apply system engineering methodologies to structure the process and allow for verification and validation of the major RV design parameters such as thickness of RV. The structural thicknesses of various part of RV are determined as well as reinforcements on the RV major nozzles. A 3D virtual reality model was created based on the design parameters using CATIA V5 and animation using Dassault Composer V2016. A comparison of re-engineered ARP1400 RV and standard APR1400 RV was done to show which design parameters were taken more conservative approach.

• 한국해양공학회지
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• 제27권1호
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• pp.9-15
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• 2013

This paper calculates the mating dynamic forces of a semi-submersible offshore structure's topside module, where a hull moored in the sea is combined with a topside module carried by a heavy lift vessel, as a mating installation method. The environmental conditions include various wave directions and wave heights, with constant wind and current speeds. Appropriate ballast and de-ballast plans for the heavy lift vessel and hull of the semi-rig should be performed in order to safely obtain these forces, whereas a fixed platform or the GBS (Gravity based structure) type of offshore structure only needs a ballast plan for the heavy lift vessel. From this paper, the allowable wave height or wave direction for the mating procedure can be investigated based on the standard DAF (Dynamic amplitude factor) of the rules and regulations.

• 한국통신학회논문지
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• 제34권5B호
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• pp.449-454
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• 2009

본 논문에서는 먼저 선박환경에서 USN 구축을 위한 하드웨어와 소프트웨어 플랫폼을 분석하였다. 하드웨어 플랫폼에서는 기존의 CC2420기반의 mote 기술을 분석하였고 소프트웨어 플랫폼에서는 TinyOS 플랫폼을 분석하였다. 다음으로 USN 통신방식의 표준인 IEEE 802.15.4의 물리계층을 분석하고 선박USN 성능분석을 위해 Matlab을 사용하여 ZigBee/IEEE 802.15.4 물리계층에 대해 성능평가를 수행하였다. 결과적으로 이동하는 선박환경에서의 선박USN 구축에 관한 타당성을 성능평가를 통해 검증하였다.

• Journal of Power Electronics
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• 제15권2호
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• pp.378-388
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• 2015

This paper proposes a pulse width modulation (PWM)-based sliding mode controller (SMC) for a full-bridge DC-DC converter that can eliminate static output voltage error. Hysteretic SMC in DC-DC converter does not have a fixed switching frequency, and applying hysteretic SMC to full-bridge converters is difficult. Fixed-frequency SMC, which is also called PWM-based SMC, based on equivalent control overcomes these shortcomings. However, the controller order reduction in equivalent control in PWM-based SMC causes static output voltage error. To resolve this issue, an integral item is added to the PWM-based SMC. Sliding mode coefficients are designed by applying a standard second-order system to the sliding mode surface. The effect of adding an integral item on the controller is analyzed, and an integral coefficient design method is proposed. Experiment results on a three-level full-bridge DC-DC converter verify the control scheme and design method proposed in this paper.

• Nuclear Engineering and Technology
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• 제53권1호
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• pp.93-102
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• 2021

The analysis of the fluid flow characteristics in reactor pressure vessel is an important part of the hydraulic design of nuclear power plant, which is related to the structure design of reactor internals, the flow distribution at core inlet and the safety of nuclear power plant. The flow distribution and mixing characteristics in the pressurized reactor vessel for the 1000MWe advanced pressurized water reactor is analyzed by using Computational Fluid Dynamics (CFD) method in this study. The geometry model of the full-scaled reactor vessel is built, which includes the cold and hot legs, downcomer, lower plenum, core, upper plenum, top plenum, and is verified with some parameters in DCD. Under normal condition, it is found that the flow skirt, core plate holes and outlet pipe cause pressure loss. The maximum and minimum flow coefficient is 1.028 and 0.961 respectively, and the standard deviation is 0.019. Compared with other reactor type, it shows relatively uniform of the flow distribution at the core inlet. The coolant mixing coefficient is investigated with adding additional variables, showing that mass transfer of coolant occurs near the interface. The coolant mainly distributes in the 90° area of the corresponding core inlet, and mixes at the interface with the coolant from the adjacent cold leg. 0.1% of corresponding coolant is still distributed at the inlet of the outer-ring components, indicating wide range of mixing coefficient distribution.

• 해양환경안전학회지
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• 제26권4호
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• pp.309-316
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• 2020

항만 진입항로 설계 시에는 선박 입출항에 따른 통항 안전성이 우선적으로 확보될 수 있도록 적정한 항로 폭이 고려되어야 한다. 통항 안전성에 요구되는 최소 항로 폭 산출은 선종별 선박의 크기와 운항 속력 등에 따라 상이하게 나타나는 조종성능을 포함한 선박 요소, 바람, 조류 및 파랑에 따른 환경적 요소, 그리고 운항자 개인별 경험과 판단력 등에 따른 인적 요소 및 해상교통량, 항해지원 시설 등의 기타 요소를 종합적으로 검토하여 결정해야 한다. 그러나, 우리나라 항로 폭 설계 기준이 국제수상교통시설협회나 미국, 일본 등의 기준과 비교할 때 단순히 선박 길이 요소만으로 산정하고 있어, 이에 대한 개선이 요구된다. 본 연구에서는 배속 선박조종시뮬레이션을 활용하여 다양한 형태의 선박 및 환경적 요소를 고려하여, 직선항로에서 일방통항에 요구되는 적정 항로 폭에 대한 평가를 실시하였다. 대표적인 연구 결과로 일반적인 운항 선속 10노트 기준 풍속 25노트의 바람과 유속 2노트의 조류, 파고 약 3 m의 파랑이 작용할 경우, 15만 GT급 크루즈선은 선박 길이(L) 대비 0.67~0.91, 1만 2천 TEU급 컨테이너선은 0.79~1.17, 30만 DWT급 원유운반선은 1.02~1.59에 해당되는 최소 항로 폭이 필요한 것으로 분석되었다. 해당 결과는 우리나라 항로 설계기준의 개선 필요성 및 선박 대형화에 따른 통항 안전성 확보에 요구되는 최소 항로 폭 결정 등에 직접적으로 활용이 가능할 것이라 판단된다.

• Journal of Advanced Marine Engineering and Technology
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• 제38권9호
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• pp.1150-1155
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• 2014

강화플라스틱(FRP) 선박은 화재 시 화염확산을 막기 위하여 관련 구조 기준에 따라 기관실 주위 벽 내부를 난연성 수지로 3회 이상 적층하거나, 이와 동등한 방열재로 둘러싸야한다. 관련 난연성 적층용 수지 및 일부 난연재료(연질폴리우레탄복합체)의 경우 선박용 물건의 형식승인 시험기준에 따라 그 성능을 평가할 수 있으나, 방열재로 빈번하게 사용되고 있는 '겔코트'에 대한 성능기준은 명확하지 않은 실정으로 난연성 수지와 화재안전성능이 비교 평가된 바 없다. 본 연구에서는 FRP 선박을 건조하는 조선소를 대상으로 설문조사를 실시하여 사용 중인 난연성 수지 3종, 겔코트 4종, 방염도료 1종 및 폴리우레탄 복합재 1종에 대해 화염전파시험과 방염성능시험을 적용하여 그 성능을 비교하였다. 화염전파시험 결과 임계열유속(CFE) 기준으로 각 종별 평균값을 비교하면 폴리우레탄 복합재, 난연성 수지, 방염도료, 겔코트 순으로 양호한 것으로 나왔고, 겔코트는 3회 도포한 것이 6회 도포한 것보다 양호한 결과를 보였다. 방염성능시험 결과 탄화면적 기준으로 각 종별 평균값을 비교하면 방염도료가 가장 좋게 나왔고 난연성 수지와 겔코트는 유사한 수준으로 나타났다.