• Nuclear Engineering and Technology
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• 제54권3호
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• pp.888-895
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• 2022

Lately, ocean nuclear power plants have attracted attention as one of diverse uses of nuclear power plants. Because ocean nuclear power plants are movable or transportable, it is necessary to analyze the thermal hydraulics in a moving frame of reference, and computer codes have been developed to predict thermal hydraulics in large moving systems. The purpose of this study is to incorporate a three dimensional dynamic motion model into the SPACE code (Safety and Performance Analysis CodE) so that the code is able to analyze thermal hydraulics in an ocean nuclear power plant. A rotation system that describes three-dimensional rotations about an arbitrary axis was implemented, and modifications were made to the one-dimensional momentum equations to reflect the rectilinear and rotational acceleration effects. To demonstrate the code's ability to solve a problem utilizing a rotational frame of reference, code calculations were conducted on various conceptual problems in the two-dimensional and three-dimensional pipeline loops. In particular, the code results for the three-dimensional pipeline loop with a tilted rotation axis agreed well with the multi-dimensional CFD results.

• Nuclear Engineering and Technology
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• 제41권7호
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• pp.953-968
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• 2009

It is important to accurately predict the temperature and density distributions in large stratified enclosures both for design optimization and accident analysis. Current reactor system analysis codes only provide lumped-volume based models that can give very approximate results. Previous scaling analysis has shown that stratified mixing processes in large stably stratified enclosures can be described using one-dimensional differential equations, with the vertical transport by jets modeled using integral techniques. This allows very large reductions in computational effort compared to three-dimensional CFD simulation. The BMIX++ (Berkeley mechanistic MIXing code in C++) code was developed to implement such ideas. This paper summarizes major models for the BMIX++ code, presents the two-plume mixing experiment simulation as one validation example, and describes the codes' application to the liquid salt buffer pool system in the AHTR (Advanced High Temperature Reactor) design. Three design options have been simulated and they exhibit significantly different stratification patterns. One of design options shows the mildest thermal stratification and is identified as the best design option. This application shows that the BMIX++ code has capability to provide the reactor designers with insights to understand complex mixing behavior with mechanistic methods. Similar analysis is possible for liquid-metal cooled reactors.

• 유체기계공업학회:학술대회논문집
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• 유체기계공업학회 2006년 제4회 한국유체공학학술대회 논문집
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• pp.241-244
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• 2006

The analysis of propellant feeding sub-system is performed using a commercial code SINDA/FLUINT, the comprehensive finite-difference, one-dimensional, lumped parameter tool. With the code, cryogenic helium supply system, liquid oxygen supply system, helium injection cooling system are evaluated. The code gave satisfactory estimation scheme for propulsion system characterized by cryogenic temperature and high pressure, two phase flow. This paper focuses on presenting calculation scheme of propulsion sub-system using one-dimensional code like SINDA/FLUINT.

• 산업기술연구
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• 제25권B호
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• pp.171-174
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• 2005

In this paper, we propose a new data encoding algorithm for a two-dimensional bar code system. In general, the one-dimensional bar code is just a key which can access detailed information to the host computer database. But the two-dimensional bar code is a new technology which can obtain high density information without access to the host computer database. We implemented the encoding algorithm for Data Matrix bar code which is the most widely used among the many kinds of two-dimensional bar codes in the field of marking using Digital Signal Processor (TMS320C31). The performance of the proposed algorithm is verified by comparing the imprinted symbols on the steel surfaces with the codes which are decoded by a bar code reader.

• Nuclear Engineering and Technology
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• 제55권9호
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• pp.3320-3325
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• 2023

The scaled water-cooled Reactor Cavity Cooling System (RCCS) experimental facility reproduces a passive safety feature to be implemented in Generation IV nuclear reactors. It keeps the reactor cavity and other internal structures in operational conditions by removing heat leakage from the reactor pressure vessel. The present work uses Flownex one-dimensional thermal-fluid code to model the facility and predict the experimental thermal-hydraulic behavior. Two representative steady-state cases defined by the bulk volumetric flow rate are simulated (Re = 2,409 and Re = 11,524). Results of the cavity outlet temperature, risers' temperature profile, and volumetric flow split in the cooling panel are also compared with the experimental data and RELAP system code simulations. The comparisons are in reasonable agreement with the previous studies, demonstrating the ability of Flownex to simulate the RCCS behavior. It is found that the low Re case of 2,409, temperature and flow split are evenly distributed across the risers. On the contrary, there's an asymmetry trend in both temperature and flow split distributions for the high Re case of 11,524.

• Nuclear Engineering and Technology
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• 제41권10호
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• pp.1347-1360
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• 2009

A multi-dimensional component for the thermal-hydraulic system analysis code, MARS, was developed for a more realistic three-dimensional analysis of nuclear systems. A three-dimensional and two-fluid model for a two-phase flow in Cartesian and cylindrical coordinates was employed. The governing equations and physical constitutive relationships were extended from those of a one-dimensional version. The numerical solution method adopted a semi-implicit and finite-difference method based on a staggered-grid mesh and a donor-cell scheme. The relevant length scale was very coarse compared to commercial computational fluid dynamics tools. Thus a simple Prandtl's mixing length turbulence model was applied to interpret the turbulent induced momentum and energy diffusivity. Non drag interfacial forces were not considered as in the general nuclear system codes. Several conceptual cases with analytic solutions were chosen and analyzed to assess the fundamental terms. RPI air-water and UPTF 7 tests were simulated and compared to the experimental data. The simulation results for the RPI air-water two-phase flow experiment showed good agreement with the measured void fraction. The simulation results for the UPTF downcomer test 7 were compared to the experiment data and the results from other multi-dimensional system codes for the ECC delivery flow.

• 한국융합학회논문지
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• 제4권3호
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• pp.27-33
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• 2013

기존의 바코드는 정보 배열이 나란히 나열된 선 모양을 가지며 이를 1차원 바코드라 부른다. 이에 반해 2차원 바코드는 점자방식 또는 모자이크방식 코드로 작은 정사각형 도는 직사각형 안에 정보를 표현한다. 2차원 바코드는 기존의 1차원 바코드보다 작은 공간에 많은 데이터를 표현 가능함으로써 보다 효율적인 바코드의 구현이 가능하다. 현재 ISO 국제 표준화된 2차원 바코드는 총 4가지로 분류되는데 QR Code, Data Matrix, PDF417, MaxiCode가 있다. 본 논문에서는 ISO 국제 표준화된 바코드 중 하나인 Data Matrix의 Base 256 모드에 대한 기본 개념, 구성 방법, 인코딩 및 디코딩 방법을 상세히 제안한다. Data Matrix 심벌에 저장된 데이터를 보다 효율적으로 구성하기 위해 숫자, Alphanumeric 문자, 이진법에 따라 다른 인코딩, 디코딩 방법을 사용하게 되는데 본 논문에서는 이를 고려한 디코딩 방법에 초점을 맞춰 기술할 것이다.

• 대한전기학회논문지:시스템및제어부문D
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• 제49권12호
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• pp.683-689
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• 2000

Two-dimensional(2-D) fiber-optic code-division multiple-access(FO-CDMA) system utilizes the optical orthogonal signature pattern code(OOSPC) to encode and decode 2-D data. Encoded 2-D data are spatially multiplexed and transmitted through an image fiber and receiver recovers the intended data by means of thresholding process. OOSPC's construction methods based on expansion of the optical orthogonal code, which is used in one-dimensional(1-D) FO-CDMA system, are introduced. Each OOSPC's performances are compared by using the bit error rate(BER) of interfering OOSPC's of other users. From the results we verify that a balanced incomplete block design(BIBD) construction has the best performance among other mehtods. We also propose a decomposed bit-plane method for parallel transmission and recovery of 256 gray-scale images using OOSPC's constructed by the BIBD method. The simulation result encourages the feasibility of parallel transmission and recovery of multiuser's images.

• Nuclear Engineering and Technology
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• 제33권2호
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• pp.209-224
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• 2001

The SSC-K system analysis code is under development at the Korea Atomic Energy Research Institute (KAERI) as a part of the KALIMER project. The SSC-K code is being used as the principal tool for analyzing a variety of off-normal conditions or accidents of the preliminary KALIMER design. The SSC-K code features a multiple-channel core representation coupled with a point kinetics model with reactivity feedback. It provides a detailed, one-dimensional thermal-hydraulic simulation of the primary and secondary sodium coolant circuits, as well as the balance-of-plant steam/water circuit. Recently a two-dimensional hot pool model was incorporated into SSC-K for analysis of thermal stratification phenomena in the hot pool. In addition, SSC-K contains detailed models for the passive decay heat removal system and a generalized plant control system. The SSC-K code has also been applied to the computational engine for an interactive simulation of the KALIMER plant. This paper presents an overview of the recent activities concerned with SSC-K code model development This paper focuses on both descriptions of the newly adopted thermal hydraulic and neutronic models, and applications to KALIMER analyses for typical anticipated transients without scram.

• 한국통신학회논문지
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• 제38A권10호
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• pp.827-832
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• 2013

홀로그래픽 데이터 저장장치에서는 인접 심볼간 간섭이 2차원으로 발생하며, 인접 페이지간 간섭 또한 발생한다. 특히 멀티 레벨 홀로그래픽 데이터 저장장치의 경우, 한 픽셀이 나타내는 정보가 0과 1의 이진수가 아닌 그 이상의 정보를 더 저장하고 있기 때문에, 위와 같은 간섭들이 더 크게 발생할 수 있다. 본 논문에서는 4-레벨 홀로그래픽 데이터 저장장치에서의 성능 저하를 보완하기 위하여 2/3 변조 부호를 제안한다. 제안된 2/3 변조 부호는 비터비 검출 방법을 변조 방식에 적용하여 에러 정정 능력을 갖는다. 또한, 본 논문에서는 2/3 변조 부호를 위한 새로운 비터비 디코더를 제안한다. 제안된 비터비 검출기는 복호 시에 필요없는 상태에 대한 계산을 제거하여 복호 성능을 높인다. 제안된 비터비 검출기는 2/3 변조 부호에 대하여 기존의 비터비 검출기보다 더 뛰어난 성능을 보인다.