• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.350.1-350
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• 1999

• 한국전산유체공학회지
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• 제8권3호
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• pp.32-40
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• 2003

CFD analyses of the three-dimensional turbulent flow in the impeller and diffuser of an axial flow pump including suction and discharge parts are presented and compared with experimental data. The purpose of the current study is to validate the CFD method for the performance analysis of the main coolant pump for SMART and to investigate the effect of suction and discharge shapes on the pump performance. To generate a performance curve, not only the design point but also the off-design points were computed. The results were compared with available experimental data in terms of head generated. At the design point, the analysis accurately predicts the experimental head value. In the range of the higher flow rates, the results are also in very good agreement with the experimental data, in magnitude but also in terms of slope of variation. For lower flow rates, the results shows that the analysis considering the suction and discharge well describe the typical S-shape performance curve of the axial pump.

• 한국소음진동공학회논문집
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• 제20권7호
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• pp.658-664
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• 2010

A control element drive mechanism(CEDM) is a reactor regulating system, which inserts, withdraws or maintains a control rod containing a neutron absorbing material within a reactor core to control the reactivity of the core. The ball-screw type CEDM for the integral reactor has a spring-damper system to reduce the impact force due to the scram of the CEDM. This paper describes the experimental results to obtain the drop and damping characteristics of the CEDM. The drop tests are performed by using a drop test rig and a facility. A drop time and a displacement after an impact are measured using a LVDT. The influences of the rod weight, the drop height and the flow area of hydraulic damper on the drop and damping behavior are also estimated on the basis of test results. The drop time of the control element is within 4.5s to meet the design requirement, and the maximum displacement is measured as 15.6 mm. It is also found that the damping system using a spring-hydraulic damper plays a good damper role in the CEDM.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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• pp.411-416
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• 1998

출력운전 동안 원자로 냉각재의 정화 없이 운전하는 SMART원자로의 수화학 설계 요건을 정립하기 위하여 핵연료 피복관 및 계통재질의 부식을 최소화하고 부식 생성물의 방사화에 의한 방사선 준위의 상승을 억제하기 위한 수화학 운전 변수에 대한 정성적인 분석을 시도하였다. 원자로냉각재 의 pH 제어 계통을 구성하는 재질의 부식에 따른 건전성, 부식생성물의 거동 및 원자로 냉각재의 방사선 준위 측면에서 수화학 설계 요건이 적절한지의 여부를 살펴보았다 분석 결과, 원자로냉각재의 pH 제어는 암모니아를 이용하므로 높은 pH(= 9.5∼10.6)에서 운전이 가능하며, 계통재질의 부식을 최소화하며 방사선 준위의 상승을 억제할 수 있었다. 또한 SMART 증기발생기 튜브에 사용된 titanium 합금은 주어진 운전 조건하에서 Inconel-600보다 내 부식성이 매우(약 12 배) 우수하였다.

• 한국유체기계학회 논문집
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• 제17권6호
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• pp.77-83
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• 2014

The vessel of integral reactor contains its major primary components such as the fuel and core, pumps, steam generators, and a pressurizer, so its size is proportional to the required space for the installation of each component. The steam generators take up the largest volume of internal space of reactor vessel and their volumes is substantial for the overall size of reactor vessel. Reduction of installation space for steam generators can lead to much smaller reactor vessel with resultant decrease of overall cost for the components and related facilities. A printed circuit heat exchanger is one of the compact types of heat exchangers available as an alternative to conventional shell and tube heat exchangers. Its name is derived from the procedure used to manufacture the flat metal plates that form the core of the heat exchanger, which is done by chemical milling. These plates are then stacked and diffusion bonded, converting the plates into a solid metal block containing precisely engineered fluid flow passages. The overall heat transfer area and pressure drops are evaluated for the steam generator based on the concept of the printed circuit heat exchanger in this study. As the printed circuit heat exchanger is known to have much larger heat transfer area density per unit volume, we can expect significantly reduced steam generator compared to former shell and tube type of steam generator. For the introduction of new steam generator, two design requirements are considered: flow area ratio between primary and secondary flow paths, and secondary side parallel channel flow oscillation. The results show that the overall volume of the steam generator can be significantly reduced with printed circuit type of steam generator.

• 한국경영과학회:학술대회논문집
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• 대한산업공학회/한국경영과학회 2004년도 춘계공동학술대회 논문집
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• pp.197-200
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• 2004

기존의 제어실 정보표시는 계통 및 기기정보를 바탕으로 하는 사건중심의 나열식 정보표시체계를 가지므로써 운전원이 표시되는 정보를 검색하고 판단하기까지는 많은 정신적 부담이 있었으며 이로 인한 운전오류가 많이 발생하였다. 이에 따라 본 논문은 일체형원자로(SMART:System-integrated Modular Advanced ReacTor) 제어실에서 운전원이 감독자 기능을 지원할 수 있도록 운전원이 쉽고 빠르게 필요한 운전정보를 검색하여 필요한 조치를 취할 수 있는 정보체계를 제안한다.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2001년도 하계학술대회 논문집 B
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• pp.705-707
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• 2001

This paper describes the finite element analysis(FEA) for the design of electromagnet for SMART CEDM and compared with the lifting power characteristics of prototype electromagnet. As a result, it is shown that the characteristics of prototype electromagnet have a good agreement with the results of FEA.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2001년도 하계학술대회 논문집 B
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• pp.774-776
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• 2001

This paper describes the finite element analysis(FEA) for the design of common core-type and separated core-type rotational speed sensor(RSS) for SMART MCP and compared with the low/ high speed characteristics of prototype RSS. As a result, it is shown that the characteristics of prototype RSS have a good agreement with the results of FEA.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2011년도 추계학술대회 논문집
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• pp.219-220
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• 2011

• 대한전기학회:학술대회논문집
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• 대한전기학회 2008년도 추계학술대회 논문집 전력기술부문
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• pp.476-478
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• 2008

분산 전원의 기저 전원으로써 개발된 일체형 원자로(REX-10)를 지역에너지시스템에 도입하고 안정적인 운전을 하기 위해서 본 논문은 전압원형 인버터를 설계하고 일체형 원자로가 변동 없이 정출력을 하도록 지역에너지시스템의 전력 변동 상황을 모니터링하여 제어하는 모델을 개발하였다. 제안된 모델의 효용성을 확인하기 위해서 PSCAD/EMTDC를 사용하였다.