• Nuclear Engineering and Technology
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• 제31권3호
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• pp.303-313
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• 1999

Various interpolation methods have been compared for reconstruction of LMR pin power distributions in hexagonal geometry. Interpolation functions are derived for several combinations of nodal quantities and various sets of basis functions, and tested against fine mesh calculations. The test results indicate that the interpolation functions based on the sixth degree polynomial are quite accurate, yielding maximum interpolation errors in power densities less than 0.5%, and maximum reconstruction errors less than 2% for driver assemblies and less than 4% for blanket assemblies. The main contribution to the total reconstruction error is made tv the nodal solution errors and the comer point flux errors. For the polynomial interpolations, the basis monomial set needs to be selected such that the highest powers of x and y are as close as possible. It is also found that polynomials higher than the seventh degree are not adequate because of the oscillatory behavior.

• 기술혁신학회지
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• 제2권3호
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• pp.118-128
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• 1999

This study attempts to provide an efficient method for managing the Nuclear R&D projects. It should be noted that the technology and experiences to develop a well-balanced plan and mon-itoring for the R&D project are not yet well established when compared with the commercial con-structionand engineering projects. This study recommends that the R&D project manager utilize the scheduling techniques to establish an integral management system taking in to account the un-certainties in the research environment. Based upon the results of a case study for the Liquid Metal Reactor Design Technology Development Project which is led by the KAERI this study also con-firms that it is possible to run the national nuclear R&D projects with the Scheduling & Planning.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(2)
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• pp.837-843
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• 1998

This paper presents the thermomechanical and fracture mechanics evaluation procedure of thermal striping damage on the secondary piping of LMFR using Green's function method and standard FEM. The thermohydraulic loading conditions used in the present analysis are simplified sinusoidal thermal loads and the random type data thermal load. The thermomechainical fatigue damage was evaluated according to ASME code subsectionNH. The analysis results of fatigue for the sinusoidal and random load cases show that fatigue failure would occur at a geometrically discontinuous location during 90,000 hours of operation The fracture mechanics analysis showed that the crack would be initiated at an early stage of the operation. The fatigue crack was evaluated to propagate up to 5 ㎜ along the thickness direction during the first 944 and 1083 hours of operation for the sinusoidal and the random loading cases, respectively.

• 유체기계공업학회:학술대회논문집
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• 유체기계공업학회 2005년도 연구개발 발표회 논문집
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• pp.240-243
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• 2005

This study deals with the shape optimization of a wire spacer fuel assembly of Liquid Metal Reactors (LMRs). The Response Surface based optimization Method is used as an optimization technique with the Reynolds-averaged Navier-Stokes analysis of fluid flow and heat transfer using Shear Stress Transport (SST) turbulence model as a turbulence closure. Two design variables namely, pitch to fuel rod diameter ratio and lead length to fuel rod diameter ratio are selected. The objective function is defined as a combination of the heat transfer rate and the inverse of friction loss with a weighting factor. Three level full-factorial method is used to determine the training points. In total, nine experiments have been performed numerically and the resulting datas have been analysed for optimization study. Also, a comparison has been made between the optimized surface and the reference one in this study.

• 유체기계공업학회:학술대회논문집
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• 유체기계공업학회 2004년도 유체기계 연구개발 발표회 논문집
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• pp.473-478
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• 2004

This work presents the Thermal Hydraulic analysis has been performed for a 19-pin wire-spacer fuel assembly using three-dimensional Reynolds-averaged Navier-Stokes equations. SST model is used as a turbulence closure. The whole fuel assembly has been analyzed for one period of the wire-spacer using periodic boundary condition at inlet and outlet of the calculation domain. The overall results far a preliminary calculation show a good agreement with the experimental observations. It has been found that the major unidirectional flows are the axial velocity in sub-channels and the peripheral sweeping flows and the velocities are found to be following a cyclic path of period equal to the wire-wrap pitch. The temperature is found to be maximum in the central region and also, there exist a radial temperature gradient between the fuel rods. The major advantage of performing this kind of analysis is the prediction of thermal-hydraulic behavior of a fuel assembly with much ease.

• 설비공학논문집
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• 제13권9호
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• pp.853-859
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• 2001

A pulsed tracer gas technique is applied to measure distributions of local mean age and residual life time of air in a half-scale experimental chamber. The room airflow patterns are flow-visualized by a Helium bubble generator for three different exhaust locations. A supply slot is located at the top of a right wall, and an exhaust slot is either at bottom-left(Case 1), bottom-right(Case 2), or top-left(Case 3) location. Results show that the distribution of LMA and LMR are different from each other, but both of them are closely related to the airflow pattern in the space. Results on overall room ventilation effectiveness are provided depending upon ventilation airflow rates for three different supply-exhaust configurations.

• 한국전산구조공학회논문집
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• 제12권4호
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• pp.583-589
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• 1999

본 논문에서는 MDO기법에 의한 핵연료교환장치의 구조해석 단계 중 핵연료교환장치의 휨 변형을 구하는 재료역학해석을 수행하였다. 이는 액체 금속로(LMR) 핵연료교환장치의 기본설계를 위하여 매우 중요하다. 해석대상 핵연료교환장치의 정적구조는 기 수행한 핵연료교환장치의 기구 동역 학 해석 결과를 활용하였다. 네 가지 핵연료교환동작에 대하여 핵연료 봉의 무게를 100㎏에서 500㎏까지 100㎏씩 증가시켜 휨 변형의 크기를 구하였다. 그 결과 회전 중심 축에서 가장 멀리 있는 핵연료 봉을 교환하는 핵연료교환동작에서 최대 휨 변형이 발생함이 밝혀졌다. 또한 이 최대 휨 변형이 발생하는 핵연료교환장치구조에 대하여 부재의 단면두께를 축소하면서, 또 단면형상을 여러 가지로 바꾸면서 휨 변형크기를 구하여 비교하였다. 비교결과 비교대상 단면형상 중에서 중공직사각형 단면이 최소 휨 변형이 발생하는 최적단면형상임이 밝혀졌다.

• Nuclear Engineering and Technology
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• 제35권2호
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• pp.121-132
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• 2003

To reduce the construction cost and enhance the safety of sodium cooled liquid metal reactors, various kinds of new design concepts were evaluated using the KALIMER operation condition. The required equipment sizes were set for plant electricity output to be similar to that of KALIMER. The evaluations were made focusing on the plant performance and implementation practicality. Each design concept was evaluated for the concept itself and design impacts to interfacing systems. Through the evaluation of the concepts, it was found that the most favorable design concept is the integrated steam generator with forced convection using lead bismuth as the intermediate heat transfer fluid between the primary sodium tube and feed water/steam tube in the steam generator.

• 비파괴검사학회지
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• 제26권5호
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• pp.297-305
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• 2006

액체금속로 원자로배플 및 상부내부구조물 등은 고온소듐의 자유액면에 접하기 때문에 소듐액면의 상하 이동으로 열 라체팅 손상이 발생할 수 있다. 액체금속로 내부구조물의 열 라체팅 변형 손상을 감지할 수 있는 가동중검사 기법의 개발이 필요하다. 본 연구에서는 유도초음파를 이용하여 원통형 내부구조물의 열 라체팅 변형 손상을 감지할 수 있는 검사 방법을 제시하였다. 원형통 구조물의 열 라체팅 변형 거동의 모사를 위해 SS 316L 재료의 원통 시험편을 제작하고 $550^{\circ}C$ 이상의 급격한 열하중을 가하면서 냉각수의 자유액면의 상하 이동 시험을 실시하였다. 스테인리스 강 재질의 박판에서의 유도초음파의 분산 특성을 분석하여 $A_0$ 모드를 열 라체팅 변형을 탐지할 수 있는 유효 모드로 선정하였다. 제작된 라체팅 변형 원통형 셀 구조물에서 원주방향으로 반복하여 회전하는 $A_0$ 모드의 전파시간차를 측정함으로써 열 라체팅 변형 탐지 가능성을 확인하였다.

• 대한기계학회논문집B
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• 제31권8호
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• pp.663-671
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• 2007

In this work, shape optimization of a wire-wrapped fuel assembly in a liquid metal reactor has been carried out by combining a three-dimensional Reynolds-averaged Navier-Stokes analysis with the radial basis neural network method, a well known surrogate modeling technique for optimization. Sequential Quadratic Programming is used to search the optimal point from the constructed surrogate. Two geometric design variables are selected for the optimization and design space is sampled using Latin Hypercube Sampling. The optimization problem has been defined as a maximization of the objective function, which is as a linear combination of heat transfer and friction loss related terms with a weighing factor. The objective function value is more sensitive to the ratio of the wire spacer diameter to the fuel rod diameter than to the ratio of the wire wrap pitch to the fuel rod diameter. The optimal values of the design variables are obtained by varying the weighting factor.