• Nuclear Engineering and Technology
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• 제36권6호
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• pp.528-539
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• 2004

It is essential in commercial reactors that the safety limits imposed on the fuel pellets and fuel clad barriers, such as the linear power density (LPD) and the departure from nucleate boiling ratio (DNBR), are not violated during reactor operations. In order to accurately monitor the safety limits of current reactor states, a detailed three-dimensional (3D) core power distribution should be estimated from the in-core detector signals. In this paper, we propose a calculation methodology for detailed 3D core power distribution, using in-core detector signals and core monitoring constants such as the 3D Coupling Coefficients (3DCC), node power fraction, and pin-to-node factors. Also, the calculation method for several core safety parameters is introduced. The core monitoring constants for the real core state are promptly provided by the core design code and on-line MASTER (Multi-purpose Analyzer for Static and Transient Effects of Reactors), coupled with the core monitoring program. through the plant computer, core state variables, which include reactor thermal power, control rod bank position, boron concentration, inlet moderator temperature, and flow rate, are supplied as input data for MASTER. MASTER performs the core calculation based on the neutron balance equation and generates several core monitoring constants corresponding to the real core state in addition to the expected core power distribution. The accuracy of the developed method is verified through a comparison with the current CECOR method. Because in all the verification calculation cases the proposed method shows a more conservative value than the best estimated value and a less conservative one than the current CECOR and COLSS methods, it is also confirmed that this method secures a greater operating margin through the simulation of the YGN-3 Cycle-1 core from the viewpoint of the power peaking factor for the LPD and the pseudo hot pin axial power distribution for the DNBR calculation.

• Nuclear Engineering and Technology
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• 제15권4호
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• pp.236-247
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• 1983

한국원자력 1호기(KNU-1)의 설계 및 운전자료를 이용하여 가압경수로 운전변수들의 변화에 대한 DNBR의 민감도를 분석하였다. 본 민감도 분석에는 원자로 출력, 압력, 냉각수 주입유량, 냉각수 주입온도, 반경방향 및 축방향 출력분포 그리고 축방향 출력편차 등의 운전변수가 고려되었다. 민감도 분석을 위하여는 노심의 열수력 해석용 전산코드인 COBRA-IV-K를 사용하였는데 본 코드는 COBRA-IV-i의 수정판으로써 한국에너지연구소에서 일부 프로그램을 수정하였고 또한 신뢰도도 확인하였다. 민감도 분석을 수행하기 전에 KNU-1 원자로심의 설계 및 운전조건을 근거로 하여 기초 계산을 수행하고 이 결과를 본 민감도 분석의 기본자료로 삼았다. 민감도 분석결과 원자로의 DNBR 열설계에 있어서 가장 민감한 운전변수는 냉각수 주입온도이고 가장 둔감한 변수는 축방향 출력분포라는 것이 밝혀졌다.

• 한국안전학회지
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• 제37권5호
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• pp.80-88
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• 2022

The Korean nuclear industry had developed the SPACE (Safety and Performance Analysis Code for nuclear power plants) code, which adopts a two-fluid, three-field model that is comprised of gas, continuous liquid and droplet fields and has the capability to simulate three-dimensional models. According to the revised law by the Nuclear Safety and Security Commission (NSSC) in Korea, the multiple failure accidents that must be considered for the accident management plan of a nuclear power plant was determined based on the lessons learned from the Fukushima accident. Generally, to improve the reliability of the calculation results of a safety analysis code, verification is required for the separate and integral effect experiments. Therefore, the goal of this work is to verify the calculation capability of the SPACE code for multiple failure accidents. For this purpose, an experiment was conducted to simulate a Control Element Drive Mechanism (CEDM) break with a safety injection failure using the ATLAS test facility, which is operated by Korea Atomic Energy Research Institute (KAERI). This experiment focused on the comparison between the experiment results and code calculation results to verify the performance of the SPACE code. The results of the overall system transient response using the SPACE code showed similar trends with the experimental results for parameters such as the system pressure, mass flow rate, and collapsed water level in component. In conclusion, it can be concluded that the SPACE code has sufficient capability to simulate a CEDM break with a safety injection failure accident.

• Nuclear Engineering and Technology
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• 제54권11호
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• pp.4134-4145
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• 2022

The collimator is one of the high-heat-flux components used to avoid a series of vacuum and thermal problems. In this paper, the heat load distribution throughout the collimator is first calculated through experimental data, and a transient thermodynamic simulation analysis of the original model is carried out. The error of the pipe outlet temperature between the simulated and experimental values is 1.632%, indicating that the simulation result is reliable. Second, the model is optimized to improve the heat transfer performance of the collimator, including the contact mode between the pipe and the flange, the pipe material and the addition of a twisted tape in the pipe. It is concluded that the convective heat transfer coefficient of the optimized model is increased by 15.381% and the maximum wall temperature is reduced by 16.415%; thus, the heat transfer capacity of the optimized model is effectively improved. Third, to adapt the long-pulse steady-state operation of the experimental advanced superconducting Tokamak (EAST) in the future, steady-state simulations of the original and optimized collimators are carried out. The results show that the maximum temperature of the optimized model is reduced by 37.864% compared with that of the original model. The optimized model was changed as little as possible to obtain a better heat exchange structure on the premise of ensuring the consumption of the same mass flow rate of water so that the collimator can adapt to operational environments with higher heat fluxes and long pulses in the future. These research methods also provide a reference for the future design of components under high-energy and long-pulse operational conditions.

• Nuclear Engineering and Technology
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• 제55권2호
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• pp.460-474
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• 2023

A simple but accurate mathematical model is crucial for dynamic simulations and controller design of helical coil once-through steam generator (OTSG). This paper presents a three-region movable boundary dynamic model of the helical coil OTSG. Based on the secondary side fluid conditions, the OTSG is divided into subcooled region (two control volumes), two-phase region (two control volumes) and superheated region (three control volumes) with movable boiling boundaries between each region. The nonlinear dynamic model is derived based on mass, energy and momentum conservation equations. And the linear model is obtained by using the transfer function and state space transformation, which is a 37-order model of five input and three output. Validations are made under full-power steady-state condition and four transient conditions. Results show good agreements among the nonlinear model, linear model and the RELAP5 model, with acceptable errors. This model can be applied to dynamic simulations and controller design of helical coil OTSG with constant primary-side flow rate.

• 한국정밀공학회지
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• 제12권11호
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• pp.27-35
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• 1995

The fluid coupling combined with a pump and a turbine have many merits compared with other couplings, their uses are increesing rapidly in various industrial fields at home and abroad in pursuit of high-speed more efficiency durability of various mechanic devices. The authorities concerned have recognized the improtance of the fluid coupling and supported its developement and now some trial products began to show up. As the structrue and characteristics of the fluid coupling have little similarity to other kinds of couplings and its fluid behavior is unique, so its characteristic analysis is expected to be difficult. Until now no satisfactory study on the characteristics of the fluid coupling seems to have been conducted at home, so a study on this field needs to be done urgently. The purpose of this research is to construct the experimental test set-ups and establish a series of performance test program for the domestically developed fluid couplings and to provide a software to store and utilize these experimental data which can be used to improve the performance of the fluid coupling and solve on the job problems confronted in operation. The performance test consists of taking measurment of torque, rpm and efficiency of the fluid coupling for three different amount of working fluid inside with various loads to the output shaft and finally infestigating the torque, rpm and efficiency characteristics of the fluid coupling with respect to these parameters. The results of this study can contribute valuable references to the development of variable speed fluid coupling and torque converter currently pursued by the domestic industry.

• 대한기계학회논문집B
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• 제35권5호
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• pp.473-480
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• 2011

막 가습기는 다른 가습장치와는 달리, 기생 전력의 손실이 없고 가습 성능이 우수하여 이온교환막 연료전지의 외부 가습을 위해 적용되고 있다. 원통형 막 가습기는 특히 가습성능에 비해 요구 체적이 매우 작기 때문에, 수송용 및 가정용 이온교환막 연료전지에 적용된다. 막가습기의 최적 설계를 위한 열 및 물질 전달 특성에 대한 이해가 필요하지만, 아직 다양한 연구가 이루어지고 있지 않다. 본 연구에서는 원통형 막가습기의 열 및 물질전달 특성을 이해하기 위한 특성 실험을 수행하였다. 기존의 습도 측정계는 비정상 가습 특성 실험에 한계가 있고, 정상 상태에서도 고온 다습한 환경에서는 오차가 크기 때문에 본 연구에서는 습증기 응축법을 이용하였다. 가습기의 정상상태 특성을 확인하기 위해 압력과 온도 변화에 대한 실험을 수행하였으며, 비정상 특성을 확인하기 위해 순간 유량 변화 시의 가습 성능을 측정하였다. 본 연구에서는 이상의 기초 실험을 통해서 막 가습기의 성능에 영향을 미치는 주요 인자를 확인하였으며, 원통형 막가습기의 기초적인 열 및 물질 전달 특성을 이해하였다.

• 한국화재소방학회논문지
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• 제26권3호
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• pp.21-28
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• 2012

비정상(unsteady) 화재성장이 발생되는 반밀폐된 구획에서 환기부족화재의 열 및 화학적 특성에 관한 FDS(Fire Dynamics Simulator)의 예측성능 평가가 수행되었다. 이를 위해 실규모 ISO 9705 표준 화재실의 출입구 폭이 0.1 m로 축소되었으며, spray 노즐을 통해 Heptane 연료유량은 선형적으로 증가되었다. 수치계산에 대한 신뢰도 확보를 위하여 동일 조건에서 수행된 실험결과와의 상세한 비교가 이루어졌다. 적절한 격자계를 이용한 FDS의 결과는 구획 내부의 온도 및 열유속(heat flux)은 비교적 잘 예측하지만, 비정상 CO 및 $CO_2$ 생성특성은 적절히 예측하지 못함을 확인하였다. 이러한 결과는 최근 수행된 유사조건의 정상상태 환기부족 구획화재에 대한 FDS 예측결과와 상반된 것으로서, 반밀폐된 구획화재 모델링에서 FDS를 이용한 비정상 CO 생성특성 예측에 상당한 주위가 요구됨을 확인하였다.

• 대한한의학회지
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• 제44권4호
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• pp.87-103
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• 2023

Backgrounds and objectives: Cardiotonic Pills^® (CP) are used for vascular diseases such as coronary diseases, atherosclerosis, and cerebral infarction. This study aimed to determine the transient effects of CP on cerebrovascular CO₂ reactivity (CVR) and erythrocyte deformability in normal subjects. Methods: This study had a crossover design and included 10 participants who were randomly allocated to 2 groups. The experimental group was given CP with water, while the control group was given only water. CVR was measured by hyperventilation-induced CVR of the middle cerebral artery (MCA) using transcranial Doppler (TCD). Erythrocyte deformability was measured using a Rheoscan-D microfluidic ektacytometer. All measurements were performed prior to and 1, 2, and 3 hours after CP or water administration. Blood pressure and heart rate were also measured before and after administration. Results: CP significantly improved CVR 3 hours after administration in the experimental group compared to the control group (p = 0.042). The corrected blood flow velocity at partial pressure of end-tidal carbon dioxide (PETCO₂) = 40mmHg (CV40) was also significantly improved 2 and 3 hours after administration in the CP group compared to the control group (p = 0.036 and p = 0.021, respectively). CP significantly improved erythrocyte deformability 3 hours after administration in the experimental group compared to the control group (p = 0.027). Mean heart rate and mean blood pressure showed no change. Conclusions: This study demonstrated that CP increases CVR and erythrocyte deformability. These results suggested that CP improves cerebral microcirculation which provide evidence for the future use of CP for prevention of ischemic stroke and neurodegenerative diseases.

• Journal of Chest Surgery
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• 제38권11호
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• pp.733-738
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• 2005

배경: 경피적 관상동맥중재술과 최소침습성 관상동맥우회술을 병합하여 시행하는 하이브리드 관상동맥우회술(hybrid coronary artery bypass surgery; hybrid CABG)는 고위험군 환자에서 심근의 불완전한 재관류가 예상되는 경우에 수술관련 유병률을 낮추고 완전 재관류화를 이루기 위하여 적용할 수 있다. 대상 및 방법: 1998년 1월부터 2004년 7월 사이에 심폐바이패스를 사용하지 않고 관상동맥우회술을 시행한 782명의 환자 중에서 수술 전, 후에 경피적 관상동맥중재술을 같이 시행한 25명$(3.2\%)$의 환자들(M : F=17:8)을 대상으로 임상적 결과 및 심혈관 조영술을 통한 개존율을 비교하였다. 결과: 수술 전에 중재술을 시행한 8예 중 7예는 최소절개 관상동맥우회술을 시행하기에 부적합한 병변에 대해서 경피적 관상동맥중재술을 시행하였고, 다른 1예는 급성심근경색증에서 culprit병변에 대한 응급 중재술후 관상동맥우회술이 필요했던 경우였다. 수술 후 중재술을 시행한 17예는 관상동맥의 중등도 병변($70\~90\%$ 협착)으로 수술 후 이식도관과의 경쟁혈류가 예상되었던 경우 8예, 관상동맥병변이 혈관 전체에 광범위하여 혈관문합이 불가능했던 경우 5예, 상행대동맥 석회화를 동반하면서 이용 가능한 동맥 우회도관의 부족 3예, 그리고 심근내 관상동맥의 주행 1예 등에서 관상동맥우회술 후에 대상혈관에 대한 경피적 중재술을 시행하였다. 관상동맥우회술시 평균 원위부 문합수는 평균 $2.3\pm1.0$ 개소였으며, 중재술로 치료된 병변의 수는 평균 $1.2\pm0.4$개소였다. 중재술 및 수술관련사망은 없었다. 중재술관련 합병증으로 심근경색이 발생한 경우 1예가 있었으며 수술관련 합병증으로는 일시적인 심방세동 5예, 수술전후 심근경색 1예, 일시적 신기능저하 1예가 있었다. 전례에서 수술 후 평균 $1.8\pm1.6$일째에 관상동맥조영술을 시행하여 모든 도관의 개존율$(100\%=57/57)$을 확인하였다 수술 전 중재 술을 시행한 1개소에서는 중재술 부위의 재협착소견이 보여 수술 후 조영술시 재풍선확장술로 치료하였다. 수술 후 추적관찰(평균 $25\pm26$개월)동안 1예에서 심부전으로 사망하였다. 생존한 환자 24예에서 술 후 평균 $9.6\pm3$개월째에 관상동맥조영술을 시행하였고 이식도관이 string 징후를 보인 1예를 제외하고 모두 개존(56/57)되어 있었으며, 약물용출형 스탠트를 시행하기 이전의 12예의 중재술 중 2예에서 $50\%$ 이상의 스텐트 협착이 있었으나 흉통의 재발은 없었다. 결론: 하이브리드 관상동맥 우회 술은 수술위험도를 낮추기 위하여 최소절개 관상동맥우회술과 병합하여 시도될 수 있을 뿐 아니라, 선택적 환자들에서는 정중 흉골절개 관상동맥우회술과 병합하여 수술관련 유병률을 낮추고 심근의 완전 재관류화를 도모할 수 있었다.