• 한국전산유체공학회지
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• 제21권3호
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• pp.89-97
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• 2016

In this study, direct code coupling, in which two codes share a single flow field, was conducted using 3-dimensional high resolution thermal hydraulics code, CUPID and 1-dimensional system analysis code, MARS. This approach provide the merit to use versatile capability of MARS for nuclear power plants and 3-dimensional T/H analysis capability of CUPID. Numerical Method to directly couple CUPID and MARS was described in this paper. The straight flow and manometer flow oscillation were calculated to verify conservation of coupled CUPID/MARS code in mass, momentum, and energy. This verification calculations indicates that the CUPID/MARS is coupled appropriately in numerical aspect and the coupled code can be applied to nuclear reactor thermal hydraulics after validation against integral transient experiments.

• Nuclear Engineering and Technology
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• 제46권5호
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• pp.655-666
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• 2014

The CUPID code has been developed at KAERI for a transient, three-dimensional analysis of a two-phase flow in light water nuclear reactor components. It can provide both a component-scale and a CFD-scale simulation by using a porous media or an open media model for a two-phase flow. In this paper, recent advances in the CUPID code are presented in three sections. First, the domain decomposition parallel method implemented in the CUPID code is described with the parallel efficiency test for multiple processors. Then, the coupling of CUPID-MARS via heat structure is introduced, where CUPID has been coupled with a system-scale thermal-hydraulics code, MARS, through the heat structure. The coupled code has been applied to a multi-scale thermal-hydraulic analysis of a pool mixing test. Finally, CUPID-SG is developed for analyzing two-phase flows in PWR steam generators. Physical models and validation results of CUPID-SG are discussed.

• 한국전산유체공학회지
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• 제16권2호
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• pp.30-48
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• 2011

A three-dimensional thermal-hydraulic code, CUPID, has been developed for the analysis of transient two-phase flows at component scale. The CUPID code adopts a two-fluid three-field model for two-phase flows. A semi-implicit two-step numerical method was developed to obtain numerical solutions on unstructured grids. This paper presents an overview of the CUPID code development and assessment strategy. The governing equations, physical models, numerical methods and their improvements, and the systematic verification and validation processes are discussed. The code couplings with a system code, MARS, and, a three-dimensional reactor kinetics code, MASTER, are also presented.

• Nuclear Engineering and Technology
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• 제44권8호
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• pp.831-846
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• 2012

KAERI has developed a two-phase CFD code, CUPID, for a refined calculation of transient two-phase flows related to nuclear reactor thermal hydraulics, and its numerical models have been verified in previous studies. In this paper, the CUPID code is validated against experiments on the downcomer boiling and moderator flow in a Calandria vessel. Physical models relevant to the validation are discussed. Thereafter, multi-scale thermal hydraulic analyses using the CUPID code are introduced. At first, a component-scale calculation for the passive condensate cooling tank (PCCT) of the PASCAL experiment is linked to the CFD-scale calculation for local boiling heat transfer outside the heat exchanger tube. Next, the Rossendorf coolant mixing (ROCOM) test is analyzed by using the CUPID code, which is implicitly coupled with a system-scale code, MARS.

• Nuclear Engineering and Technology
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• 제42권6호
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• pp.636-655
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• 2010

A thermal-hydraulic code, named CUPID, has been being developed for the realistic analysis of transient two-phase flows in nuclear reactor components. The CUPID code development was motivated from very practical needs, including the analyses of a downcomer boiling, a two-phase flow mixing in a pool, and a two-phase flow in a direct vessel injection system. The CUPID code adopts a two-fluid, three-field model for two-phase flows, and the governing equations are solved over unstructured grids with a semi-implicit two-step method. This paper presents an overview of the CUPID code development and assessment strategy. It also presents the code couplings with a system code, MARS, and, a three-dimensional reactor kinetics code, MASTER.

• 한국전산유체공학회지
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• 제20권4호
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• pp.14-20
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• 2015

Without electirc power to cool down the hot reactor core, passive systems utilizing natural circulation are becoming a big specialty of recent neculear systems after the severe accident in Fukusima. When we consider the natural circulation in a pool, thermal mixing phenomena may start from single phase circulation and can continue to two phase condition. Since the CUPID code, which has been developed for two-phase flow analysis, can deal with the phase transition phenomena, the CUPID would be pertinent to natural convection problems in single- and two-phase conditions. Thus, the CUPID should be validated against single- and two-phase natural circulation phenomena. For the first step of the validation process, this study is focused on the validation of single-phase natural circulation. Moreover, the CUPID code solves the fluid properties by the relationship to pressure and temperature from the steam table considering non-condensable gas effects, so that the effects from variable properties are included. Simple square thermal cavity problems are tested for laminar and turbulent conditions against numerical and experimental data. Throughout the investigation, it is found that the variable properties can affect the flow field in laminar condition, but the effect becomes weak in turbulence condition, and the CUPID code implementing steam table is capable of analyzing single phase natural circualtion phenomena.

• 대한두개안면성형외과학회지
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• 제11권1호
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• pp.19-22
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• 2010

The author presents a new method for the formation of Cupid's bow and the vermilion tubercle by using the inferior-based lip skin flap in a secondary bilateral cleft lip deformity. The length of the flap includes the entire length of the previous upper lip scar. Both skin flaps are elevated and turned down toward the central part of the vermilion. The distant portion of the turned-down skin flaps are deepithelialized and trimmed according to the new shape of Cupid's bow. The deepithelialized portions of both flaps are buried under the central vermilion mucosa in order to create the vermilion tubercle. The advantages of the proposed procedure are; provision of a more natural shape of Cupid's bow, the lip length is increased, and the vermilion tubercle can be reconstructed at the same time. Therefore, this technique is best suited for a case of a bilateral absence of Cupid's bow combined with a short lip in a sufficient upper lip of a bilateral cleft lip deformity. The proposed procedure, however, should be avoided in the tight upper lip because of a great deal of tension on the donor.

• Nuclear Engineering and Technology
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• 제54권11호
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• pp.4338-4347
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• 2022

The CUPID code was developed and is continuously updated in KAERI. Verification and validation (V&V) is mainly done for light water reactors (LWRs). This paper describes a benchmarking of the detailed mesh level compared with sub-channel level for application to pressurized heavy water reactors (PHWRs), even though component scale comparison for the PHWR moderator system was done once before. We completed a sub-channel level comparison between the CUPID code and the ASSERT code and a CUPID code analysis. Because the ASSERT code has already been validated with numerous experiments, benchmarking with the ASSERT code will offer us more trust on the CUPID code. The target channel has high power and thus high pressure deformation. The high power channel tends to have a high possibility of critical heat flux (CHF), because a high void fraction and quality in channel exit region appear. In this research, after determining the reference grid and T/H model, we compared the sub-channel level results of the CUPID code with those of the ASSERT code.

• 에너지공학
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• 제21권4호
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• pp.419-426
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• 2012

본 연구에서는 기기 스케일 2상 유동(Two-phase flow) 해석 코드 CUPID를 사용하여 CANDU 원자로의 칼란드리아 용기 내부 감속재의 열수력 거동을 분석하기 위한 사전연구를 수행하였다. 먼저, Stern 연구소에서 수행한 단상유동 실험 3종류를 이용하여 CUPID 코드를 검증하였다. 칼란드리아 관다발 영역 격자생성의 복잡성을 피하기 위하여 다공성 매질 모델을 해당 영역에 적용하였고, 다공성 매질 영역의 유동 저항은 실험에서 얻은 관계식을 이용하여 계산하도록 하였다. 계산결과, CUPID 코드는 칼란드리아 용기 내부의 강제 및 자연 대류의 혼합 유동 양식을 성공적으로 예측하였다. 다음으로 2상 유동이 발생하는 경우를 해석하였다. 이들 계산을 통해 CUPID 코드의 CANDU 원자로 감속재 해석 능력을 보였다. 또한, 국부 과냉각 여유도를 예측하는데 사용할 수 있는 유입유량 대비 칼란드리아 용기의 국부 최대 감속재 온도 그래프를 제시하였다.

• 에너지공학
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• 제23권4호
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• pp.95-105
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• 2014

CUPID 코드는 기기 스케일(Component scale)의 2상 유동(Two-phase flow) 해석 코드로서 다양한 2상 유동 조건의 실험 자료를 이용하여 검증되어 왔다. 특히, CUPID 코드의 CANDU형 원자로 감속재 탱크 내부 유동 해석능력을 평가하기 위해 1/4 규모 축소 실험장치의 실험결과를 이용하여 검증한 바가 있다. 본 연구에서는 이전 연구를 바탕으로 CUPID 코드를 사용하여 실제 원자로 감속재탱크 내부의 열수력 거동을 해석하였다. 감속재 탱크의 내부 구조는 아주 복잡하기 때문에 다공질 매질 방법을 적용하였으며 탱크 입구노즐 또한 기기 스케일 코드의 취지에 부합하게 아주 단순화하여 모델하였다. 해석결과의 정확성을 결정하는 가장 중요한 요소는 입구노즐의 모델 방법에 있는 것으로 나타났다. 입구노즐을 단순하게 모델하여 입구유량을 경계조건으로 부여하고 발전소 정상운전조건으로 계산한 결과, 부력에 의한 열성층화 현상이 발생하였다. 이는 전혀 타당하지 않은 것으로 입구 유동의 모멘텀을 정확하게 모의하지 않아 발생한 것이 나타났다. 이를 개선하고자 입구 유량과 운동량을 동시에 보존시킬 수 있도록 입구 노즐 면적을 축소하고 속도는 증가시켜서 계산한 결과, 사실적인 내부 유동장을 얻을 수 있었다. 결론적으로 계산 비용효과가 뛰어난 다공질 매질 방법에 입각하여 CUPID 코드를 실규모 감속재 탱크 열유동 해석에 적용할 수 있음을 보였고, 입구노즐의 적절한 모델이 가장 중요한 요소임을 확인하였다.