• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(1)
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• pp.429-436
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• 1995

This paper describes a methodology for determination of representative CANDU feeder geometry and the pressure drops between inlet/outlet header and fuel channel in the primary loop. A code, MEDOC, was developed based on this methodology and helps perform a calculation of equivalent feeder geometry for a selected channel group on the basis of feeder geometry data (fluid volume, mass flow rate, loss factor) and given property data pressure, quality, density) at inlet/outlet header. The equivalent feeder geometry calculated based on this methodology will be useful fur the transient thermohydraulic analysis of the primary heat transport system for the CANDU heavy water-cooled pressure tube reactor.

• Journal of Mechanical Science and Technology
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• 제20권7호
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• pp.1030-1042
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• 2006

An experimental study has been performed to investigate the off-take phenomena at the header-feeder systems (horizontal header pipe with multiple feeder branch pipes) in a CANDU (CANadian Deuterium Uranium) reactor with the branch orientation varies ${\pm}36^{\circ}\;or\;{\pm}72^{\circ}$. In order to evaluate the applicability of the conventional correlations used in the safety analysis code, RELAP5-Mod3, the test facility is designed with the 1/2 scale of the. CANDU 6. It was found that the data set for the top, bottom and side branches are in a good agreement with the correlations used. However, for the specific angled branches, ${\pm}36^{\circ}\;and\;{\pm}72^{\circ}$, the onsets of off-take data and quality data showed large deviation with the conventional model inside RELAP5-MOD3. Furthermore, based on the uncertainty analysis, the conventional 2.5 power law needs to be modified. The present experimental data set can be useful for the construction of the general correlation considering the arbitrary branch orientation.

• Nuclear Engineering and Technology
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• 제36권2호
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• pp.142-152
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• 2004

The liquid entrainment and vapor pull-through offtake model of RELAP5/MOD3 had been developed for SBLOCA (Small Break Loss of Coolant Accident). The RELAP5/MOD3 model for horizontal volumes accounts for the phase separation phenomena and computes the flux of mass and energy through a branch when stratified conditions occur in the horizontal pipe. In the case of CANDU reactor, this model should be used in the coolant flow of 95 feeders connected to the reactor header component under the horizontal stratification in header. The current RELAP5 model can treat the only 3 directions junctions; vertical upward, downward, and side oriented junctions, and thus improvements for the liquid entrainment and vapor pull-through model were needed for considering the exact angles. The RELAP5 off-take model was modified and generalized by considering the geometric effect of branching angles. Based on the previous experimental results, the critical height correlation was reconstructed by use of the branch line connection angle and validation analyses were also performed using SET. The new model can be applied to vertical upward, downward and angled branch, and the accuracy of the new correlations is more improved than that of RELAP5.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2003년도 춘계학술발표대회 요약집
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• pp.120-120
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• 2003

• 한국시뮬레이션학회논문지
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• 제15권4호
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• pp.59-67
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• 2006

본 연구에서는 갠트리타입 기종을 사용한 PCB 조립 생산시 생산시스템의 수행도 향상을 위한 방안을 개발하여 제시한다. 갠트리타입의 기종에서는 헤더나 슬롯의 이동보다는 노즐의 교체가 시스템의 수행도 향상에 주된 걸림돌이 되므로 동시흡착을 최대화할 수 있는 방안을 모색하였다. 본 연구에서 제시된 해법은 피더의 위치와 노즐의 위치를 감안하여 동시흡착을 수행하도록 함으로써 노즐 교체를 최소화하고, 기판당 조립시간의 감소도 이루어지도록 하였다. 제안 해법의 유효성을 입증하기 위해 시뮬레이션 모형을 구축하고 부품의 수를 변화시켜가면서 다음 작업대상피더와 교체노즐의 선정을 다양하게 하여 여러 운영방안들의 수행도와 비교 분석하였다. 시뮬레이션 결과, 동시흡착을 유도하는 노즐교체를 할 경우 전반적인 수행상태가 양호한 것으로 나타났다.