• Nuclear Engineering and Technology
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• 제13권1호
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• pp.1-11
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• 1981

가압경수로심의 3차원적 simulation 코드인 KINS를 개발하여 고리1호기 제 1주기에 대한 benchmark 계산을 수행하였다. KINS는 FLARE에서 사용하고 있는 모델을 기초로 하여 가압경수로심 해석에 보다 유용하게 쓸 수 있도록 발전시킨 것이다. 제 1주기초에서는 hot zero power 상태에서의 임계붕소농도, 핵연료집합체별 출력분포, 노심평균축방향 출력분포 등을 계산하여 실측 자료와 비교하였다. 아울러 연소도 1000MWD/MTU 단위로 연소계산을수행하여 여기서 산출된 임계 붕소농도와 핵 연료집합체별 출력 분포를 실측자료와 비교하였다. 계산결과는 실측자료와 매우 훌륭하게 일치하고 있으므로 KINS가 가압경수로의 노심관리에 아주 경제적이며 유효한 도구가 될것임을 보여주는 것이라고 생각된다.

• Corrosion Science and Technology
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• 제18권2호
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• pp.61-71
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• 2019

Flow-Accelerated Corrosion (FAC) is a phenomenon in which a protective coating on a metal surface is dissolved by a flow of fluid in a metal pipe, leading to continuous wall-thinning. Recently, many countries have developed computer codes to manage FAC in power plants, and the FAC prediction model in these computer codes plays an important role in predictive performance. Herein, the FAC prediction model was developed by applying a machine learning method and the conventional nonlinear regression method. The random forest, a widely used machine learning technique in predictive modeling led to easy calculation of FAC tendency for five input variables: flow rate, temperature, pH, Cr content, and dissolved oxygen concentration. However, the model showed significant errors in some input conditions, and it was difficult to obtain proper regression results without using additional data points. In contrast, nonlinear regression analysis predicted robust estimation even with relatively insufficient data by assuming an empirical equation and the model showed better predictive power when the interaction between DO and pH was considered. The comparative analysis of this study is believed to provide important insights for developing a more sophisticated FAC prediction model.

• Journal of Radiation Protection and Research
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• 제30권3호
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• pp.121-130
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• 2005

고리 원전 주변 지역에서 가상사고 시에 발생하는 핵종 방출 후 토양 또는 농작물에서 시간 경과에 따라 변화하는 핵종 농도분포를 도식적으로 표현하기 위한 GIS를 구축하였다. 이를 위해 ESRI 사의 GIS 구축용 상용 프로그램인 ArcView를 도입하였다. 미리 고리원전 주변의 북서방향 $20km{\times}20km$ 구역에 대한 1:5000 축적의 지도 데이터를 구축하였다. 표현 대상 농작물 및 방출핵종은 주민의 주식인 쌀과 $^{131}I$로 정하였다. 총 100개의 cell에서 $^{131}I$의 침적량으로부터 토양 및 농작물 부분에 대한 $^{131}I$의 시간에 따른 양을 ECOREA-II코드를 통해 계산하였다. 계산결과를 ArcView에서 미리 준비된 polygon cell의 속성 자료에 각각의 cell id와 일치시켜 데이터 병합(join) 작업을 수행하였다. 시간이 경과됨에 따라 낮아지는 $^{131}I$ 농도값을 일관성있는 색상 변화로 나타내기 위해 ArcView의 color lamp에 대한 RGB 값을 조절하였다. 이 방법을 이용하여 고리주변의 북서방향 $10km{\times}10km$ 지역에서 $^{131}I$의 침적 후 쌀에서 시간에 따라 변하는 $^{131}I$ 농도분포를 일관성있는 색상 변화로 쉽게 구분이 되도록 나타낼 수 있었다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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• pp.108-113
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• 1996

Several analytical models for the departure from nucleate boiling (DNB) phenomenon have been developed during the last decade. Among these, Chang & Lee's model based on a bubble crowding mechanism is remarkable in the fundamental features characterized as the formulation of mass, energy, and momentum balance equation at thermal-hydraulic conditions leading to the DNB. However, Bricard and Souyri remarked that the assumption of stagnant bubbly layer at the DNB condition is questionable and the signs on the axial projections of the momentum fluxes at the core/bubbly layer interface in the momentum balance equations are erroneous. From this remark, Chang & Lee's model has been re-examined and modified by correcting the erroneous treatments in the momentum balance equations and removing the spurious assumptions. The revised model predicts well the extensive DNB data of water in uniformly heated tubes at low qualities and shows more accurate prediction compared with the original model.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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• pp.273-278
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• 1997

Critical two-phase flow rates of subcooled water through very short tube (L=20 mm) with small diameters (D=1.0 mm) has been measured for wide ranges of subcooling(0~186$^{\circ}C$) and pressure (0.5~2.0 MPa). Experimental results show that subcooled critical two-phase flow rates can be expressed in terms of two scaling parameters for geometries and initial conditions. They are discharge coefficient of cold water, ( $C_{d}$ )$_{ref}$, and dimensionless subcooling, $\Delta$ $T^{*}$$_{sub}$, respectively. A new empirical correlation expressed in terms of ( $C_{d}$ )$_{ref}$ and $\Delta$ $T^{*}$$_{sub}$ is obtained for subcooled two-phase flow rates through very short length tube. Comparisons between the mass fluxes calculated by Present correlation and a number of experimental data show that the agreement is very good.ood.ood.ood.

• Nuclear Engineering and Technology
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• 제26권3호
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• pp.389-400
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• 1994

FLECHT SEASET 실험 데이터를 사용하여 대형 냉각재 상실 사고시 재관수 첨두 피복재 온도에 대한 RELAP5 /MOD3/KAERI의 예측능력을 평가하였으며, 관련 불확실성을 통계적으로 정량화 하였다. 중력구동 재관수 실험및 광범위한 재관수율, 시스템 압력, 초기 피복재 온도, 연료봉 출력을 포괄하는 강제구동 재관수 실험들로 구성된 18개의 실험이 평가에 사용되었다. 평가 결과 재관수 첨두 피복재 온도에 대해 평균 7.56 K 낮게 예측하였으며 이를 포함한 관련 불확실성의 상한은 95% 신뢰도 수준에서 약 99 K로 정량화 되었다.

• Nuclear Engineering and Technology
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• 제25권2호
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• pp.259-264
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• 1993

조사후핵연료의 연소도측정에 1-octanesulfonate 를 양이온 교환체로 사용하고 $\alpha$-hydroxyisobutyric acid를 용리액으로 사용하는 동적계의 이온크로마토그래피를 적용하였다 Pu, U 및 Nd의 최적 분리조건을 찾기위해 분리조건들을 변화하였다. 이들 원소들을 $\alpha$-hydroxyisobutyric acid 용리액을 0.05 M과 0.40 M을 혼합시키는 기울기용리법으로 개별 분리한후 분취하여 동위원소희석 질량분석법으로 각각 정량하였다. 본 방법에 의래 구한 연소도 값을 기존의 음이온교환수지법에 의한 값과 비교한 결과 3.5 %차이 이내에서 두 값이 서로 일치하였다.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.299-303
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• 2001

Using ultrasound techniques, the Korea Atomic Energy Research Institute has measured chest wall thicknesses of a group of male workers at the Korea Atomic Energy Research Institute. A site-specific biometric equation has been developed for these workers. Chest wall thickness is an important modifier on lung counting efficiency. These data have been put into the perspective of the ICRP recommended dose limits for occupationally exposed workers: 100 mSv in a 5-year period with a maximum of 50 mSv in anyone year. For measured chest wall thicknesses of 1.9 cm to 4.1 cm and a 30 min counting time, the achievable MDAs for natural uranium in the KAERI lung counter vary from 5.75 mg to 11.28 mg. These values are close to, or even exceed, the predicted amounts of natural uranium that will remain in the lung (absorption type M and S) after an intake equal to the Annual Limit on Intake corresponding to a committed dose of 20 mSv. This paper shows that the KAERI lung counter probably cannot detect an intake of Type S natural uranium in a worker with a chest wall thickness equal to the average value (2.7 cm) under routine counting conditions.

• Nuclear Engineering and Technology
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• 제33권1호
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• pp.73-82
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• 2001

Pressurized water reactor(PWR) fuel rods. which are continuously supported by a spring system called a spacer grid(SG), are exposed to reactor coolant at a flow velocity of up to 6-8 m/s. It is known that the vibration of 3 fuel rod is generated by the coolant flow, a so-called flow-induced-vibration(FIV), and the relative motion induced by the FIV between the fuel rod and the SG can wear away the surface of the fuel rod, which occasionally leads to its fretting failure. It is, therefore, important to understand the vibration characteristics of the fuel rod and reflect that in its design. In this paper, vibration analyses of the fuel rod with two different SGs were performed using both analytical and experimental methods. Updating of the finite element(FE) model using the measured data was performed in order to enhance confidence in the FE model of fuel rods supported by an SG. It was found that the modal parameters are very sensitive to the spring constant of the SG.

• Nuclear Engineering and Technology
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• 제43권3호
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• pp.309-316
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• 2011

Molybdenum is the most abundant fission product since its fission yield is equivalent to that of xenon, and it has a very special role in the chemistry of nuclear fuel because it influences the oxygen potential of $UO_2$ fuel. In this study, the distribution of molybdenum in spent $UO_2$ fuel specimens with 33.3, 41.0 and 57.6 GWd/tU burnup was measured by a LA-ICP-MS system and the reproducibility of the measured data was obtained. The Mo distribution was almost constant along the radius of a fuel except an increase at the periphery of the fuel. It showed a drop in reproducibility with relatively high deviation of measured values for the highest burnup fuel. To explain this, the state of molybdenum in a $UO_2$ matrix and its effect on the oxidation behavior of $UO_2$ were investigated. The low reproducibility was explained by the segregation of molybdenum, and the inhibition of oxidation by the molybdenum was also observed.