• Title/Summary/Keyword: 집합관

Search Result 93, Processing Time 0.023 seconds

Structural Integrity of a Fuel Assembly for the Secondary Side Pipe Breaks (2차측 배관파단에 대한 핵연료 집합체의 구조 건전성)

  • Jhung, M. J.
    • Journal of KSNVE
    • /
    • v.6 no.6
    • /
    • pp.827-834
    • /
    • 1996
  • The effect of pipe breaks in the secondary side is investigated as a part of the fuel assembly qualification program. Using the detailed dynamic analysis of a reactor core, peak responses for the motions induced from pipe breaks are obtained for a detailed core model. The secondary side pipe breaks such as main steam line and economizer feedwater line braksare considered because leak-before-break methodology has provided a technical basis for the elimination of double ended guillotine breaks of all high energy piping systems with a diameter of 10 inches or over in the primary side from the design basis. The dynamic responses such as fuel assembly shear force, bending moment, axial force and displacement, and spacer grid impact loads are carefully investigated. Also, the stress analysis is performed and the effect of the secondary side pipe breaks on the fuel assembly structural integrity under the faulted condition is addressed.

  • PDF

Homogenization of KMRR Hafnium Control Assembly for 3-D Diffusion Calculation (3차원 중성자 확산계산을 위한 KMRR Hafnium 조정집합체 균질화에 대한 연구)

  • Park, Hang-Bok;Kim, Young-Jin;Kim, Hark-Rho;Lee, Ji-Bok
    • Nuclear Engineering and Technology
    • /
    • v.20 no.4
    • /
    • pp.233-240
    • /
    • 1988
  • The hafnium shroud is used to control the excess reactivity and power distribution in KMRR. The core analysis is performed by the diffusion code VENTURE using the 5 group macroscopic cross sections homogenized for an assembly. Investigated are the applicability of the diffusion calculation by homogenized cross sections to the analysis of control assembly which features unusual geometry such that hafnium shroud surrounds a multiplying medium inside. Comparative calculation is performed for the excess reactivity and power levels by the transport code TWOTRAN. The results show the acceptability of the diffusion calculation by the homogenized cross sections without significant error.

  • PDF

A Study on the Organization of Literary Archives as National Cultural Heritage (국가문화유산으로서 문학기록의 조직화 방안)

  • Lee, Eun Yeong
    • The Korean Journal of Archival Studies
    • /
    • no.61
    • /
    • pp.31-69
    • /
    • 2019
  • This study seeks to find an organizational method suitable for literary records through a review of the application of records management and an archival exploration of the literary materials of the authors, which are housed in a decentralized collection of domestic literary museums. First, through literature research and case analysis, I explored the "principles of original order" for organizing by characteristics and values of literary records. Next, the organization model was applied to the literature materials of author Jo Jung-rae(1943~) that existed in the form of a 'split-collection' in the local literature museum after drawing a model suitable for organizing literary records as an example. In order to gain an integrated approach to the 'split-collection' by Cho Jung-rae, the research result suggests a model provided through a single gateway by linking descriptive information related to ICA AtoM-based 'Records-Writers-Literature Museum'. The organizational model for the collection of individual literature museum was designed to provide richer collective and contextual information compared to the existing simple list by developing a hierarchical classification system in accordance with the principle of record organizing.

Deep Learning Models for Autonomous Crack Detection System (자동화 균열 탐지 시스템을 위한 딥러닝 모델에 관한 연구)

  • Ji, HongGeun;Kim, Jina;Hwang, Syjung;Kim, Dogun;Park, Eunil;Kim, Young Seok;Ryu, Seung Ki
    • KIPS Transactions on Software and Data Engineering
    • /
    • v.10 no.5
    • /
    • pp.161-168
    • /
    • 2021
  • Cracks affect the robustness of infrastructures such as buildings, bridge, pavement, and pipelines. This paper presents an automated crack detection system which detect cracks in diverse surfaces. We first constructed the combined crack dataset, consists of multiple crack datasets in diverse domains presented in prior studies. Then, state-of-the-art deep learning models in computer vision tasks including VGG, ResNet, WideResNet, ResNeXt, DenseNet, and EfficientNet, were used to validate the performance of crack detection. We divided the combined dataset into train (80%) and test set (20%) to evaluate the employed models. DenseNet121 showed the highest accuracy at 96.20% with relatively low number of parameters compared to other models. Based on the validation procedures of the advanced deep learning models in crack detection task, we shed light on the cost-effective automated crack detection system which can be applied to different surfaces and structures with low computing resources.

Expression of HSP70 Immunoreactivity in EPO Treated Rat Kidney (콩팥에서 Erythropoietin 투여로 인한 HSP70의 발현 변화)

  • Jung, Ju-Young;Kim, Jin
    • Applied Microscopy
    • /
    • v.37 no.3
    • /
    • pp.167-174
    • /
    • 2007
  • Heat shock protein (HSP) 70 functions as a molecular chaperon and reduces stress-induced denaturation and aggregation of intracellular proteins. Erythropoietin (EPO) plays an important role during acute renal failure repair process by rapidly correcting anemia and enhancing renal tubular regeneration. The purpose of this study was to examine the effect of EPO treatment on renal HSP70 expression. Male Sprague-Dawley rats were injected rHUEPO. Kidney were preserved by in vivo perfusion with paraformaldehyde-lysine-periodate (PLP) and processed for immunohistochemistry and electron microscopy. In control kidney, HSP70 was expressed in the cortex, outer medulla and inner medulla. Especially, HSP immunoreactiviy was mainly founded in descending thin limb of outer medulla and inner medullary collecting duct. In EPO treated kidney, HSP70 expression markedly increased in the descending thin limb of outer medulla and newly detected in cortical collecting duct. Electron microscopy showed the presence of HSP immunoreactivity on the intracelluar vesicles and Golgi complex of descending thin limb and cortical collecting duct. These findings suggest that EPO treatment leads to new production of HSP70 in renal tubular cells, and induction of HSP70 by rHuEPO is causally related to protective function.

The Characteristics and Optical Implementation of OA-pSDF BPOF (OA-pSDF BPOF의 특성 및 광학적 구현)

  • 임종태;박성균;엄주욱;박한규
    • The Journal of Korean Institute of Communications and Information Sciences
    • /
    • v.19 no.8
    • /
    • pp.1433-1445
    • /
    • 1994
  • In this paper, an coherent optical correlator system based on the off-axis projection synthetic discriminant funtion (OA-pSDF) was analyzed and implemented optically. The filter was synthesized by combining conventional pSDF with single reference plane wave multiplexing. Synthesized pSDF were transformed to binary phase only filters (BPOFs) and fabricated as computer generated holograms(CGHs), which was used in the real time optical correlator system instead of using expensive spatial light modulators(SLMs). From the characteristic test, it was found that OA-pSDF showed distortion invariance and good performances in discrminating subset images. The proposed OA-pSDF BPOF could overcome the limitations of conventional BPOFs : that is distortion variance such as acale and rotation, especially out of plane variance.

  • PDF

Shape Optimization of Internally Finned Tube with Helix Angle (나선형 핀이 내부에 부착된 관의 형상최적화)

  • Kim, Yang-Hyun;Ha, Ok-Nam;Lee, Ju-Hee;Park, Kyoung-Woo
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
    • /
    • v.19 no.7
    • /
    • pp.500-511
    • /
    • 2007
  • The Optimal solutions of the design variables in internally finned tubes have been obtained for three-dimensional periodically fully developed turbulent flow and heat transfer. For a trapezoidal fin profile, performances of the heat exchanger are determined by considering the heat transfer rate and pressure drop, simultaneously, that are interdependent quantities. Therefore, Pareto frontier sets of a heat exchanger can be acquired by integrating CFD and a multi-objective optimization technique. The optimal values of fin widths $(d_1,\;d_2)$, fin height(h) and helix angle$(\gamma)$ are numerical1y obtained by minimizing the pressure loss and maximizing the heat transfer rate within ranges of $d_1=0.5\sim1.5mm$, $d_2=0.5\sim1.5mm$, $h=0.5\sim1.5mm$, and $\gamma=0\sim20^{\circ}$. For this, a general CFD code and a global genetic algorithm(GA) are used. The Pareto sets of the optimal solutions can be acquired after $30^{th}$ generation.

An Application of Multi-Objective Global Optimization Technique for Internally Finned Tube (휜형 원형관의 형상 최적화를 위한 다목적 전역 최적화 기법의 응용)

  • Lee, Sang-Hwan;Lee, Ju-Hee;Park, Kyoung-Woo
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
    • /
    • v.17 no.10
    • /
    • pp.938-946
    • /
    • 2005
  • Shape optimization of internally finned circular tube has been peformed for periodically fully developed turbulent flow and heat transfer. The physical domain considered in this study is very complicated due to periodic boundary conditions both streamwise and circumferential directions. Therefore, Pareto frontier sets of a heat exchanger can be acquired by coupling the CFD and the multi-objective genetic algorithm, which is a global optimization technique. The optimal values of fin widths $(d_1,\;d_2)$ and fin height (H) are numerically obtained by minimizing the pressure loss and maximizing the heat transfer rate within ranges of $d_1=0.2\sim1.5\;mm,\;d_2=0.2\sun1.5\;mm,\;and\;H=0.2\sim1.5\;mm$. The optimal values of the design variables are acquired after the fifth generation and also compared to those of a local optimization algorithm for the same geometry and conditions.

3D Finite Element Simulation of Pellet-Cladding Mechanical Interaction (3차원 유한요소를 이용한 핵연료와 피복관 기계적 거동 해석)

  • Seo, Sang Kyu;Lee, Sung Uk;Lee, Eun Ho;Yang, Dong Yol;Kim, Hyo Chan;Yang, Yong Sik
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.40 no.5
    • /
    • pp.437-447
    • /
    • 2016
  • In a nuclear power plant, the fuel assembly, which is composed of fuel rods, burns, and the high temperature can generate power. The fuel rod consists of pellets and a cladding that covers the pellets. It is important to understand the pellet-cladding mechanical interaction with regard to nuclear safety. This paper proposes simulation of the PCMI. The gap between the pellets and the cladding, and the contact pressure are very important for conducting thermal analysis. Since the gap conductance is not known, it has to be determined by a suitable method. This paper suggests a solution. In this study, finite element (FE) contact analysis is conducted considering thermal expansion of the pellets. As the contact causes plastic deformation, this aspect is considered in the analysis. A 3D FE module is developed to analyze the PCMI using FORTRAN 90. The plastic deformation due to the contact between the pellets and the cladding is the major physical phenomenon. The simple analytical solution of a cylinder is proposed and compared with the fuel rod performance code results.

CANDU-6 Heat Transport System Stability Analysis With Canflex Fuel Bundle (CANFLEX 핵연료를 사용한 CANDU-6의 열수송계통 안정성 분석)

  • Shin, Jung-Cheol;Park, Ju-Hwan;Kim, Tae-Han;Suk, Ho-Chun
    • Nuclear Engineering and Technology
    • /
    • v.27 no.3
    • /
    • pp.358-373
    • /
    • 1995
  • The Heat Transport system loop stability of CANDU-6 reactor using the CANFLEX fuel bundle was studied. The Thermal-hydraulic behavior of CANFLEX fuel bundle is similar to the conventional 37-element fuel bundle since the reactor power and the frictional pressure drop through the fuel channel is almost the same each other, Mounter the CANFLEX fuel bundle gives higher critical channel power and more homogeneous enthalpy distributions in the subchannels than 37-element fuel bundle. The SOPHT modelling or the CANFLEX fuel bundle and the Reactor outlet Header(ROH) interconnection line was made and the stability analysis response of Wolsong-1 reactor with CANFLEX fuel bundle was obtained. Without the ROH interconnection line the Heat Transport system loop using 43-element fuel bundle is unstable like the current 37-element fuel bundle. With the ROH interconnection line, however, the Heat Transport system is stable within $\pm$1% of nominal flow. In the Heat Transport system loop stability point of view for Wolsong-1 plant therefore, the CANFLEX fuel loading is considered to be acceptable.

  • PDF