• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.46-51
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• 1997

최근 경수로 핵연료 손상 원인 중의 하나인 연료봉 마모(Fretting Wear)가 지지격자의 스프링력 저하뿐만 아니라 원자로 냉각재 유동에 기인한 집합체 진동(Self-excited Fuel Assembly Vibration)에 의해 유발될 수 있는 것으로 밝혀져 해외 연료공급자들은 새로운 연료개발시 집합체 유동시험을 수행하여 냉각재 유동에 의한 집합체 진동 여부를 확인하고 있다. 본 연구에서는 경수로 핵연료집합체에 대한 모드해석 및 진동시험으로부터 고유진동수 및 진동모드형태를 구하여 모의 집합체 유동시험 결과와 비교 평가하였고 냉각재 유동에 의해 과도한 집합체 진동이 발생됨을 확인하였으며 가연성흡수봉집합체를 삽입한 경우에 대한 유동시험 결과와도 비교하였다. 또한, 이들 집합체의 진동 변위량과 손상 연료의 마모량 분포의 상관성을 비교 평가하였다.

• Proceedings of the Korean Society of Tribologists and Lubrication Engineers Conference
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• 2002.05a
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• pp.73-79
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• 2002

Fretting wear test in room temperature air was performed to evaluate the wear mechanism of fuel rod using a fretting wear tester, which has been developed for experimental study. The main focus was to compare the wear behaviors of fuel rod against support springs at different contact geometries (i.e. concave and convex) and slip directions (axial and transverse). The wear on the tube was examined by the surface roughness tester, which measures the volume. The result indicated that with change of contact geometry from 5N of normal load to 0.1mm gap, wear volume of tube Increased in the condition of concave spring, but slowly decreased in convex spring. From the results of SEM observation, wear mechanism of each test condition was also depend on the above contact parameters. The wear mechanism of each test condition in room temperature air is discussed.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.40 no.5
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• pp.329-337
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• 2016

As a turbulence-enhancing device, a mixing vane, which is installed at a spacer grid of the fuel assembly, plays an important role in improving convective heat transfer by generating either swirl flow in the subchannels or cross flow between the fuel rod gaps. Therefore, both the geometric configuration and the arrangement pattern of a mixing vane are important factors in determining the performance of a mixing vane. In this study, in order to examine the flow-distribution features inside a $5{\times}5$ fuel assembly with split-type mixing vanes, which was used in the benchmark calculation of the OECD/NEA, we conduct simulations using the commercial computational fluid dynamics software, ANSYS CFX R.14. We compare the predicted results with measured data obtained from the MATiS-H (Measurement and Analysis of Turbulent Mixing in Subchannels-Horizontal) test facility. In addition, we discuss the effect of the split-type mixing vanes on the flow pattern inside the fuel assembly.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2005.11a
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• pp.503-506
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• 2005

The PWR Nuclear Fuel assembly consists of more than 250 fuel rods that are supported by leaf springs in the cells of more than 10 Spacer Grids (SG) along the rod length. Since it is not easy to conduct mechanical tests on a full-scale model basis, the small-scaled rod bundle (5$\times$5) is generally used for various performance tests during the development stage. As one of the small-scaled tests, a flow test should be carried out in order to verify the performance of the spacer grid like the coolant mixing performance and to obtain the Flow-Induced Vibration (FIV) characteristics of the rod bundle over the specified flow range. A vibration test should be also performed to obtain the modal parameters of the bundle prior to the flow test. In this study, we want to develop the estimation procedure of the damping ratio for the small scaled test bundle. For the damping factor of the rod bundle and the grid case at the first vibration mode, as one of the vibration tests, a so-called pluck testing has been performed in air as a preliminary test prior to in-flow damping measurement test. Logarithmic decrement method is used for calculation of the damping ratio. Estimated damping ratio of the rod bundle is about 0.7% with reasonable error of 2% for the previous results. Nonlinear behavior of the rod bundle might be stem mainly Iron the rod-grid support configuration.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.31 no.10
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• pp.999-1008
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• 2007

The spacer grid set is a component in the nuclear fuel assembly. The set supports the fuel rods safely. Therefore, the spacer grid set should have sufficient strength for the external impact forces such as earthquake. The fretting wear occurs between the spring of the fuel rod and the spacer grid due to flow-induced vibration. Conceptual design of the spacer grid set is performed based on the Independence Axiom of axiomatic design. Two functional requirements are defined for the impact load and the fretting wear, and corresponding design parameters are selected. The overall flow of design is defined according to the application of axiomatic design. Design for the impact load is carried out by using nonlinear dynamic analysis to determine the length of the dimple. Topology optimization is carried out to determine a new configuration of the spring. The fretting wear is reduced by shape optimization using the homology theory. The deformation of a structure is called homologous if a given geometrical relationship holds before, during, and after the deformation. In the design to reduce the fretting wear, the deformed shape of the spring should be the same as that of the fuel rod. This condition is transformed to a function and considered as a constraint in the shape optimization process. The fretting wear is expected to be reduced due to the homology constraint. The objective function is minimizing the maximum stress to allow a slight plastic deformation. Shape optimization results are confirmed through nonlinear static analysis.

• Transactions of the Korean Society of Mechanical Engineers
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• v.13 no.4
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• pp.572-582
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• 1989

Elastic deformations of an infinitely long strip and a beam loaded by uniform pressure upon their upper surfaces, with the fixed-free end dondition, are considered within the range of small strains. All local governing equations are satisfied up to first order in strains, and to take into account the higher order terms neglected in the local governing equations, the overall equilibrium is imposed exactly up to the leading order. The success of the approach relies upon the semi-inverse method and the decomposition of deformations in which the classical linear theory guides the solution. The solution bridges the gap between the two extremes-the classical solutions valid only for infinitesimal deformations and the solutions form the technical theories for deformations with large rotations. The solutions may be used to confirm the technical theories and to verify numerical solutions obtained from finite element analysis.

• Applied Microscopy
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• v.34 no.2
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• pp.83-93
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• 2004

Integumentary structures of the rockfish, Sebastiscus tertius were examined by means of the light and transmission electron microscopy. Stratified epidermal layer consists of supporting cells, unicellular glands, granular cells and mitochondria-rich cells. The epidermal layer could be classified into superficial, intermediate and basal layer by morphology and structure of the supporting cells. Mucous cells of unicellular gland were observed in the superficial and intermediate layer of the epidermis. The mucous materials were identified as acidic and carboxylated mucosubstance by histochemical methods. Club cell has well-developed central vacuole, rough endoplasmic reticula and Golgi complex in the cytoplasm. Granular cells were observed in the superficial layer and contained numerous granules of high electron density. Mitochondria-rich cells are characterized by well-developed microfilaments in cortex and numerous tubular mitochondria in medullar cytoplasm. Three types of pigment cells in the dermal layer could be distinguished with electron density of cytoplasmic inclusions.

• Nuclear Engineering and Technology
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• v.25 no.4
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• pp.552-560
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• 1993

In this study, the detailed fuel assembly stress analysis model to evaluate the structural integrity for seismic and blowdown accidents is developed. For this purpose, as the first step, the program MAIN which identifies the worst bending mode shaped fuel assembly(FA) in core model is made. And the finite element model for stress calculation of FA components is developed. In the model the fuel rods (FRs) and the guide thimbles are modelled by 3-dimensional beam elements, and the spacer grid spring is modelled by a linear and relational spring. The constraints come from the results of the program MAIN. The stress analysis of the 16$\times$16 type FA under arbitary seismic load is performed using the developed program and modelling technique as an example. The developed stress model is helpful for the stress calculation of FA components for seismic and blowdown loads to evaluate the structural integrity of FA.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.40 no.12
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• pp.815-824
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• 2016

The fuel assembly for pressurized water reactor (PWR) consists of fuel rod bundle, spacer grid and bottom/top end fittings. The cooling water in high pressure and temperature is introduced in lower plenum of reactor core and directed to upper plenum through the subchannel which is formed between the fuel rods. The main thermal-hydraulic performance parameters for the PWR fuel are pressure drop and critical heat flux in normal operating condition, and quenching time in accident condition. The Korea Atomic Energy Research Institute (KAERI) has been developing an advanced PWR fuel, dual-cooled annular fuel and accident tolerant fuel for the enhancement of fuel performance and the localization. For the key thermal-hydraulic technology development of PWR fuel, the KAERI LWR fuel team has conducted the experiments for pressure drop, turbulent flow mixing and heat transfer, critical heat flux(CHF) and quenching. The computational fluid dynamics (CFD) analysis was also performed to predict flow and heat transfer in fuel assembly including the spent fuel assembly in dry cask for interim repository. In addition, the research cooperation with university and nuclear fuel company was also carried out to develop a basic thermal-hydraulic technology and the commercialization.

• Korean Journal of Environment and Ecology
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• v.7 no.1
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• pp.22-28
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• 1993

Recently, by fast industralization and development without environmental concern, our environment deterioration have being continued rapidly. Therefore, many species is placed on crisis of extinction or was already extincted by habitat destruction. In Minjujisan area, there is a plan to construct the Sport and Leisure Complex by which convert the forest conservancy district to the district of development promotion and district of sighseeing and leisure by Yongdong District. To investigate the avifauna impacts by habitat destruction, bird censuses was carried out before the Sport and Leisure Complex be construct in Minjujisan and Sokgisan area during 4-5 May, 1992 and 16-21 June, 1992. Total 229 birds of 41 species in 23 family of 9 orders were recorded during censuses. Sitta europaea amurensis was the most abundant species and Parus ater amurensis, Phylloscopus borealis xanthodryas, Parus major wladiwostokensis, Parus palustris hellmayri, and Turdus pallidus were dominant species. Accipiter nisus nisosimilis, Accipiter soloenis, and Otus scops stictonotus were found out to the natural monuments in this suvey. Halcyon pileate was observed to a rare bird in this surveyed area. Species diversity of this census was 3.381 which showed slightly higher degree than other surveyed area. The area of Minjujisan, Sokgipong, and Samdopong which have little pollution agent around there and kept away from mankind were approved the heavy avifauna area which have so many bird species. Biogeographically, the Taebaek Mountains was connected with the Sobaek Mountains through this area, therefore it was significant that many animal species could be move to each mountains ranges. The construction plan of the Sport and Leisure Complex in Minjujisan area should be restrain with concern about environmentally destruction by the Muju Resort in Dokyusan National Park which connected to that area have master plan to development the ski slopes for the 1997 Universiad with permission by the Ministry of Environment.