• 대한전기학회논문지:전기기기및에너지변환시스템부문B
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• 제49권5호
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• pp.320-326
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• 2000

The canned motor of 3-phase induction is used for main coolant pump(MCP). The type of motor is canned-motor that stator and rotor are welded by sealed can. So, cooling water flows in the air gap of the canned motor as an independent cycling cooling system from the air gap to yoke of the motor to prevent high temperature of stator can and to lubricate bearing. Heat exchange is occurred between cooling water in the air gap and cooling water from the exterior pump to prevent rising of temperature in the motor. I has to analyze the characteristics of can exactly because the loss and the heat in the can are very important to design MCP. Therefore, thermal analysis is studied considering the effect of eddy-current los induced in the can.

• 한국산학기술학회논문지
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• 제14권5호
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• pp.2069-2074
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• 2013

내연기관 차량에 전자기식 클러치 워터펌프의 적용은 연비 향상 및 배기가스 저감을 꾀할 수 있다. 이러한 클러치 워터펌프는 엔진 냉각시스템의 유량 단속에 의하여 최적 운전 조건을 가능케 한다. 본 연구에서는 클러치 워터펌프를 이용한 냉각시스템을 제어함으로써 디젤 차량의 연비 및 배기가스 특성을 살펴보았다. 전자기식 클러치 워터펌프에 의한 저온 시동시 냉각수 흐름을 차단하여 아이들 조건에서 예열 시간을 기존 워터펌프 대비 49% 정도 단축시켰고, 주행 중에는 냉각수가 최적 고온상태를 유지하도록 제어하였다. 그리하여 NEDC 모드에서 연소 효율이 개선되어 최대 5% 정도의 연비 향상 효과를 나타내었다. 또한 NOx를 제외한 HC, CO 및 $CO_2$ 배기가스의 농도가 전반적으로 감소하였다.

• 한국산학기술학회논문지
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• 제20권12호
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• pp.69-75
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• 2019

본 연구의 목적은 EV 경상용차에 적용되는 히트펌프 시스템에 대한 냉방 성능 특성을 실험적으로 분석하는 것이다. EV 경상용차가 운전되는 냉방 운전조건인 외기온도 35 ℃, 내기온도 25 ℃ 상황에서, 히트펌프 시스템의 냉방 특성을 분석하고자, 냉각수의 온도조건, 전동식 압축기 회전수 조건 변화에 대해서, 실험을 진행하였고, 그 결과를 분석하였다. 전동식 압축기 회전수가 증가할수록 냉방 성능이 평균 8.0 %가 증가하였고, 전동식 압축기 소비전력은 27 %가 증가하여서, 시스템 효율은 16.4 %가 감소하는 결과를 보여주고 있다. 전자장비 냉각을 위한 냉각수의 폐열을 활용하기 위하여서, 냉매랑 냉각수가 열교환 하는 칠러를 본 시스템에 적용하였다. 칠러에 적용되는 냉각수의 온도를 35 ℃에서 55℃로 변화시켰을 때, 응축 열원의 증가로 인하여서, 시스템 효율이 평균적으로 18.2 %가 떨어지는 결과를 보여주고 있다. 냉각수 유량 변화 측면에서, 운전 조건을 변화시켰지만, 냉방 성능에는 큰 변화를 보이고 있지 않았다. 향후, 냉각수 폐열을 사용하여서, 히트펌프 시스템에 대한 난방 성능 향상을 위한 연구가 필요한 상황에서, 관련 연구에 추가 할 예정이다.

• 한국산학기술학회논문지
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• 제5권3호
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• pp.227-231
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• 2004

It is the common features of the integral reactors that the main components of the RCS are installed within the reactor vessel, and so there are no any flow pipes connecting the steam generator or the pump whose type is the axial flow. Due to no any flow pipes, it is impossible to measure the differential pressure at the RCS of the integral reactors, and it also makes impossible measure the flow-rate of the reactor coolant. As a alternative method, the method by the measurement of the pump power of the axial flow pump has been introduced in this study. Up to now, we did not found out a precedent which the pump power is used for the flow-rate calculation at normal operation of the commercial nuclear power plants. The objective of the study is to embody the flow-rate calculation method by the measurement of the pump power in an integral reactor. As a result of the study, we could theoretically reason that the capacity-head curve and capacity-shaft power curve around the rated capacity with the high specific-speeded axial flow pumps have each diagonally steep incline but show the similar shape. Also, we could confirm the above theoretical reasoning from the measured result of the pump motor inputs. So, it has been concluded that it is possible to calculate the flow-rate by the measurement of the pump motor inputs.

• 한국유체기계학회 논문집
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• 제5권1호
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• pp.49-54
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• 2002

HANARO, 30 MW of research reactor, was installed at the depth of 13m in an open pool. The $90\%$ of primary coolant was designed to pass through the core and to remove the reaction heat of the cote. The rest, $10\%$, of the primary coolant was designed to bypass the core. And the reactor coolant through and bypass the core was inhaled at the top of chimney by the coolant pump to prevent the radiated gas from being lifted to the top of reactor pool. But, the part of core bypass coolant was not inhaled by the reactor coolant pump and reached at the top of reactor pool by natural convection, and increased the radiation lovel on the top of reactor pool. To reduce the radiation level by protecting the natural convection of the core bypass flow, the hot water layer (HWL, hereinafter) was installed with the depth of 1.2 m from the top of reactor pool. As the HWL was normally operated, the radiation level was reduced to five percent ($5\%$) in comparing with that before the installation of the HWL. When HANARO was operated at a higher temperature than the normal temperature of the HWL by operating the standby heater, it was found that the radiation level was more reduced than that before operation. To verify the reason, the heat loss of the HWL was calculated by Visual Basic Program. It was confirmed through the results that the larger the temperature difference between the HWL and reactor hall was, the more the evaporation loss increased. And it was verified that the radiation level above was reduced mote safely by increasing the capacity of heater.

• 유체기계공업학회:학술대회논문집
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• 유체기계공업학회 2001년도 유체기계 연구개발 발표회 논문집
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• pp.221-226
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• 2001

HANARO, 30MW of research reactor, was installed at the depth of 13m of open pool, The $90\%$ of primary coolant was designed to pass through the core and to remove the reaction heat of the core. The rest $10\%$, of the primary coolant was designed to bypass the core. And the reactor coolant through and bypass the core was inhaled at the top of chimney by the coolant pump to protect that the radiated gas was lifted to the top of reactor pool. But, the part of core bypass coolant was not inhaled by the reactor coolant pump and reached at the top of reactor pool by natural convection and increased the radiation level on the top of reactor pool. To reduce the radiation level by protecting the natural convection of the core bypass flow, the hot water layer (HWL, hereinafter) was installed with the depth of 1.2m from the top of reactor pool. As the HWL was normally operated, the radiation level was reduced to five percent ($5\%$) in comparing with that before the installation of the HWL. When HANARO was operated with higher temperature than the normal temperature of the HWL by operating the standby heater, it was found that the radiation level was more reduced than that before operation. To verify the reason, the heat loss of the HWL was calculated. It was confirmed through the results that the larger the temperature difference between the HWL and reactor hall was, the more the evaporation loss was increased. And it was verified that the radiation level above was reduced more safely by increasing the capacity of heater.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 춘계학술발표회요약집
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• pp.491.1-491
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• 2001

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 추계학술발표회요약집
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• pp.369-369
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• 1998

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 추계학술발표회요약집
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• pp.110.2-110
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• 2001

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 추계학술발표회요약집
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• pp.353.1-353
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• 2001