• Nuclear Engineering and Technology
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• 제17권1호
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• pp.16-24
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• 1985

풀형 고속증식로에서의 과도 현상을 모사할 수 있는 전산 모델이 개발되었다. 이 전산 모델 SIM-FARP는 어떠한 펌프로의 전원 상실사고나 완전한 강제냉각 상실사고, 그리고 자연순환 과정 등을 모사할 수 있는 Fast Running Computer Code이다. 이에 따라 8개의 지배방정식이 유도되었으며, 이8개의 미분 방정식을 풀기 위해 Runge-Kutta의 수치해석방법이 사용되었다. 개발된 전산 프로그램은 두 가지 예제에 적용되었는데 이는 Super-Phenix-I에서의 펌프에의 전원상실사고 및 원자로가 정지되지 않는 상태에서의 외부전원 상실사고이다.

• 한국진공학회:학술대회논문집
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• 한국진공학회 2012년도 제43회 하계 정기 학술대회 초록집
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• pp.180-180
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• 2012

Heteroepitaxial GaN nano- and micro-rods (NMRs) are one of the most promising structures for high performance optoelectronic devices such as light emitting diodes, lasers, solar cells integrated with Si-based electric circuits due to their low dislocation density and high surface to volume ratio. However, heteroepitaxial GaN NMRs growth using a metal-organic vapor phase epitaxy (MOVPE) machine is not easy due to their long surface diffusion length at high growth temperature of MOVPE above $1000^{\circ}C$. Recently some research groups reported the fabrication of the heteroepitaxial GaN NMRs by using MOVPE with vapor-liquid-solid (VLS) technique assisted by metal catalyst. However, in the case of the VLS technique, metal catalysts may act as impurities, and the GaN NMRs produced in this mathod have poor directionallity. We have successfully grown the vertically well aligned GaN NMRs on Si (111) substrate by means of self-catalystic growth methods with pulsed-flow injection of precursors. To grow the GaN NMRs with high aspect ratio, we veried the growth conditions such as the growth temperature, reactor pressure, and V/III molar ratio. We confirmed that the surface morphology of GaN was strongly influenced by the surface diffusion of Ga and N adatoms related to the surrounding environment during growth, and we carried out theoretical studies about the relation between the reactor pressure and the growth rate of GaN NMRs. From these results, we successfully explained the growth mechanism of catalyst-free and mask-free heteroepitaxial GaN NMRs on Si (111) substrates. Detailed experimental results will be discussed.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2003년도 춘계학술대회논문집
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• pp.683-688
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• 2003

Vibration characteristics of a fuel rod to be used in KALIMER(Korean Advanced LIquid MEtal Reactor) have been estimated through 3-dimensional finite element analysis and verified by experiment. The fundamental natural frequencies are found to be 6㎐ in air and 2.5㎐ in water. respectively. It has been found that in-water natural frequencies of the fuel rod are lower than in-air ones due to the added mass effect of the fluid filled inside the outer cylinder and they further decreases as the gap between the fuel rod and the outer cylinder increases, namely the added mass effect increases as the gap increases(maximum 54%). It has been also shown that the mass of the wire wrap axially coiled around the fuel rod do not affect the natural frequencies.

• Nuclear Engineering and Technology
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• 제33권3호
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• pp.298-306
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• 2001

As fuel burnup proceeds, thermal gradients, differential swelling, and inter-assembly loading may induce assembly duct bowing. Since duct bowing affects the reactivity, such as long or short term power-reactivity-decrement variations, handling problem, caused by top end deflection of the bowed assembly duct, and the integrity of the assembly duct itself. Assembly duct bowing were first observed at EBR-ll in 1965, and then several designs of assembly ducts and core restraint system were used to accommodate this problem. In this study, NUBOW-2D KMOD was used to analyze the bowing behavior of the assembly duct under the KALIMER(Korea Advanced Liquid MEtal Reactor) core restraint system conditions. The mechanical behavior of assembly ducts related to several design parameters are evaluated. ACLP(Above Core Load Pad) positions, the gap distance between the ducts, and the gap distance between the duct and restraint ring were selected as the sensitivity parameter for the evaluation of duct deflection.

• Nuclear Engineering and Technology
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• 제33권2호
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• pp.145-155
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• 2001

This simulation first allows us to define a transition zone from a bubble to jet mode of the argon out-flow and hereinafter to define a similar area for water-steam leak in the KALIMER SG (Korea Advanced Liquid Metal Reactor Steam Generator) using a water mock-up system, taking into account the KALIMER leak classification and tube bundle design, as a simulation of a real water-steam into sodium leak. in accordance with leak conditions in the KALIMER SG, the transition from bubbling to jetting is studied by means of turbulence regime simulation for argon out-flow through a very small orifice, which has the equivalent diameter of about 0.253 mm. finally the noise generation mechanism is explained from the existing experimental data. We also confirmed the possibility of micro-leak detection from the information of the bubbling mode through simulations and the experiment in this study.

• 공업화학
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• 제24권2호
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• pp.165-170
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• 2013

초고온가스로 핵연료 구형 UCO (uranium oxycarbide) 입자 제조과정 중 중간화합물 제조에서 적용하고 있는 내부겔화공정을 대체하기 위해 외부겔화공정을 도입하는 연구가 진행 중에 있다. 외부겔화공정을 이용해서 구형 UCO입자를 제조하기 위한 사전실험으로, 중간화합물인 ADU (ammonium di-uranate) 겔 입자를 제조하기 위한 원료용액인 모사 broth 용액을 제조하여 카본블랙 입자를 분산시키는 실험이 수행되었다. 다양한 종류의 카본블랙 입자를 사용해서 모사 broth 용액에 분산실험을 수행한 결과, Cabot G 제품이 용액상에서 분산안정성과 균일한 분산상태를 나타내고 있어서, 본 연구의 카본블랙으로 선정되었다. 또한 나노크기 입자로 응집된 카본블랙 입자를 고점성 액상물질에 효율적으로 분산시키기 위해서는, 금속염용액에 카본블랙 입자를 투입하고 ultrasonic force를 이용해서 응집입자를 해체한 다음, 고점성 물질인 PVA (poly vinyl alcohol)를 투입하여 강력한 기계식혼합기를 이용해서 6000 rpm으로 2차 분산 혼합시키는 경우, ultrasonic force에 의한 broth 용액의 물성이 유지되면서 카본블랙 입자의 분산안정성과 분산상태가 양호한 broth용액을 얻을 수 있었다.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2728-2735
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• 2022

The research on the flow and heat transfer characteristics of lead bismuth(LBE) is significant for the thermal-hydraulic calculation, safety analysis and practical application of lead-based fast reactors(LFR). In this paper, a new CFD model is proposed to solve the thermal-hydraulic analysis of LBE. The model includes two parts: turbulent model and turbulent Prandtl, which are the important factors for LBE. In order to find the best model, the experiment data and design of 19-pin hexagonal rod bundle with spacer grid, undertaken at the Karlsruhe Liquid Metal Laboratory (KALLA) are used for CFD calculation. Furthermore, the turbulent model includes SST k - 𝜔 and k - 𝜀; the turbulent Prandtl includes Cheng-Tak and constant (Pr_t =1.5,2.0,2.5,3.0). Among them, the combination between SST k - 𝜔 and Cheng-Tak is more suitable for the experiment. But in the low Pe region, the deviation between the experiment data and CFD result is too much. The reason may be the inlet-effect and when Pe is in a low level, the number of molecular thermal diffusion occupies an absolute advantage, and the buoyancy will enhance. In order to test and verify versatility of the model, the NCCL performed by the Nuclear Thermal-hydraulic Laboratory (Nuthel) of Xi'an Jiao tong University is used for CFD to calculate. This paper provides two verification examples for the new universal model.

• Nuclear Engineering and Technology
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• 제54권3호
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• pp.860-866
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• 2022

An accurate prediction of the pressure drop along the flow paths is crucial in the design of advanced passive systems cooled by heavy liquid metal coolants. To date, a generic pressure drop correlation over spacer grids by Rehme has been applied extensively, which was obtained from substantial experimental data with multiple types of components. However, a few experimental studies have reported that the correlation may give large discrepancies. To provide a more reliable correlation for ring-type spacer grids, the current numerical study aims at figuring out the most critical factor among four hypothetical parameters, namely the flow area blockage ratio, number of fuel rods, type of fluid, and thickness of the spacer grid in the flow direction. Through a set of computational fluid dynamics simulations, we observed that the flow area blockage ratio dominantly influences the pressure loss characteristics, and thus its dependence should be more emphasized, whereas the other parameters have little impact. Hence, we suggest a new correlation for the drag coefficient as C_B = C_ν,m/ε^2.7, where C_ν,m is formulated by a nonlinear fit of simulation data such that C_ν,m = -11.33 ln(0.02 ln(Re_b)).

• 한국지진공학회논문집
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• 제2권4호
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• pp.73-86
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• 1998

본 논문의 목적은 현재 국내에서 개발중인 KALIMER(Korea Advanced Liquid Metal Reactor) 액체금속로의 면진설계지침서에 포함될 고감쇠 적층고무베어링에 대한 전단 강성 평가법 히스테레틱 거동해석법 그리고 대변형에서의 종국거동 해석법을확립하고자하는데 있다 이를 위하여 1/8축소규모의 고감쇠 적층고무베어링을 설계제작하고 특성실험을 수행하여 제안된 전단강성식의 타당성을 검토하였다 그리고 비선형 수정 Rate 모델을 사용한 적층고무베어링의 히스테레틱 거동해석을 수행하기 위하여 히스테레틱실험결과로부터 성능특성식을 구하고 이를 1자유도계를 이용한 지진해석에 적용하여 실험결과와 비교함으로서 제안된 모델의 정확성을 입증하였다 본 논문에서 사용한 고감쇠 적층고무베어링에 대한 대변형에서의 안정성을 평가하기 위하여 수정 Macro 모델을 이용한 종국거동해석을 수행하였다 종국거동 해석결과로부터 안정성평가를 위하여 안정전단변형한계(Critcal shear strain)를 정의하였으며 해석결과 수직하중이 증가함에 따라서 안정전단변형한계가 급격히 감소함을 알수 있었다 본논문에 사용된 고감쇠 적층고무베어링은 설계수직하중에 대해서는 종국거동에서이 존재하지 않았으나 설계수직하중의 약 5배가 작용할 경우가 350% 전단변형률부터 불안정 천이현상이 발생하였으며 약 7배가 작용할 경우에 안정전단변형한계는 340%로 나타났다.

• 기술경영경제학회:학술대회논문집
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• 기술경영경제학회 1997년도 제12회 동계학술발표회 논문집
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• pp.159-176
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• 1997

This paper deals with demand surveys for big science and technology research facilities and equipments to advance national S'||'&'||'T research infrastructure. We perform surveys thrice based on applied Delphi method on the future demand of big S'||'&'||'T research facilities and equipments among Korean scientists and engineers. We employ the concept of big S'||'&'||'T research facilities and equipments as follows: \circled1 The operating size of it is equivalent to that of an institute or research center, and/or \circled2 The users in various disciplines are many, and/or \circled3 The application areas or spill-over effects are large, and/or \circled4 The scale and scope of research objects is equivalent to that of mega science area such as earth.oceanography.space, and/or \circled5 The expenses for installing and operating it are to be supported by government, and/or \circled5 The facilities are expected as necessary for international joint research, and/or \circled7 It is necessary for promoting creative basic science and developing creative technology. We ask the respondents to answer the following questionnaire: - How to prioritize the equipments according to the degree of importance\ulcorner $\square$ Promotion of basic science and mega science, the development of the technologies to enhance the public welfare, the competitiveness of industrial technologies, the job creation for the S'||'&'||'T personnel, and international cooperation. - Who should be in charge of acquisition and operation of the equipments\ulcorner $\square$ Industry, Government Research Institutes, Academy, ERC and SRC. - When shall we acquire the equipment\ulcorner $\square$ Within 2000, 2002, 2007, 2012, and 2017. - How shall we acquire the equipments\ulcorner $\square$ International Joint Development, Domestic Development, Acquisition from Overseas, - How much will the equipment generate spill-over effects to national competitiveness\ulcorner $\square$ Promotion of basic science, contribution to the economy, supply of S'||'&'||'T personnel, and international cooperation. We suggest the following equipments as prioritized candidates after consulting the officers from MOST, MOE, MIC, MOEN and experts from KBSI and STEPI:(table omitted) where, #1, Korea Advanced Liquid Metal Reactor, #2. 800 MHz Superconduction Fourier-Transform Nuclear Magnetic Resonance Spectrometer, #3. Ion Accelerator, #4. Seismic Test Facility, #5. Transonic Wind Tunnel, #6. Radio Telescope for Very Long Baseline Interferometer, #7. 3000t Universal(or Large Structure) Testing Machine, #8. Compost Facility or Plasma Pyrolysis Facility.