• 한국통신학회논문지
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• 제24권12A호
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• pp.1939-1947
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• 1999

본 논문에서는 이진데이터의 고속전송을 위하여 기존의 선로 부호의문제점을 해결하는 새로운 형태의 선로부호 BIM(Bit Insertion and Manipulation) 선로부호를 제안하였다. 기존의 이진데이터 고속전송을 위한 mBnB 형태의 블록 부호는 전송 특성은 우수하나 구현이 어려운 단점이 있었으며, 또 다른 형태의 선로 부호인 비트 삽입 부호는 구현은 용이하나 전송 특성이 떨어지는 문제점이 있었다. 본 논문에서의 BIM 선로 부호는 이러한 문제를 극복하기 위하여 제안되었으며 비트 삽입 부호에 블록 부호의 특성을 적절히 결합함으로써 구현이 용이하면서도 우수한 전송 특성을 제공할 수 있었다. 본 논문에서 설계된 5B6B 형태의 BIM 부호는 $\pm$2 DSV, 0 RSD, 7 최대 런 길이와 같이 우수한 전송 성능뿐 아니라 1비트의 리던던시만을 필요로 하며 200 게이트 이하로 구현이 가능함으로써 구현의 용이성을 함께 보여 주었다.

• ETRI Journal
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• 제34권4호
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• pp.637-640
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• 2012

The Davey-MacKay construction is a promising concatenated coding scheme involving an outer $2^k$-ary code and an inner code of rate k/n, for insertion-deletion-substitution channels. Recently, a lookup table (LUT)-based inner decoder for this coding scheme was proposed to reduce the computational complexity of the inner decoder, albeit at the expense of a slight degradation in word error rate (WER) performance. In this letter, we show that negligible deterioration in WER performance can be achieved with an LUT as small as $7{\cdot}2^{k+n-1}$, but no smaller, when the probability of receiving less than n-1 or greater than n+1 bits corresponding to one outer code symbol is at least an order of magnitude smaller than the WER when no LUT is used.

• 한국정보과학회논문지:소프트웨어및응용
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• 제37권10호
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• pp.773-778
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• 2010

국제 웹 어플리케이션 보안 연구 단체(OWASP)는 2007년에 이어 2010년에도 취약점 대부분이 사용자의 외부 데이터 입력에 기인한 것으로 발표했다. 이러한 오염된 입력 데이터는 실행 시점에서 결정되기 때문에 동적인 취약점 분석이 필요하다. 동적 분석 방법은 주로 실행 시점의 데이터 분석이나 경로 흐름 분석을 위해 인스트루먼트를 코드 내에 삽입 한다. 하지만 직접적인 코드의 삽입은 관리와 확장이 어려워 분석 범위와 대상이 증가할 때 마다 코드 조각들이 흩어지게 된다. 게다가 인스트루먼트 모듈과 시험 대상 모듈 간의 결합도가 높아진다. 따라서 개발이나 유지보수 단계에서 삽입한 분석 코드를 수정하거나 확장하는데 많은 노력이 필요하게 된다. 본 논문은 이러한 문제점을 해결하기 위해 AOP를 이용하여 취약점을 하나의 관심사로 분류함으로써 결합도의 증가 없이 삽입, 삭제와 유연한 확장이 용이한 방법을 제안한다.

• 소음진동
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• 제10권1호
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• pp.49-56
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• 2000

In this paper performance of the noise barrier which is 53 m long and 6m high, and is located between the high rise apartment and road, is studied by using experimental and analytic method. The insertion loss is measured by using the direct method in accordance with the ISO code, while theoretical prediction is based on Muradali and Fyfe's method (Applied Acoustics, Vol. 53, 49~75, 1998). In addition to the diffraction at the top of the barrier, the waves are reflected infinite times between the building and the barrier, which is equivalent to replacing the building by the infinite series of the image receiver points. In two-dimensional study, the prediction of the insertion loss results in significantly overestimated values compared with the measurement. However three-dimensional analysis shows reasonable agreements, where traffic noise is assumed as incoherent line source and the length of the source is larger than that of the barrier.

• Nuclear Engineering and Technology
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• 제52권9호
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• pp.1990-1997
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• 2020

To support the safe operation of the Miniature Neutron Source Reactor (MNSR), a thermo-hydraulic transient model using the RELAP5/Mod3.2 code was simulated. The model was verified by comparing the results with the measured and the previously calculated data. The comparisons consisted of comparing the MNSR parameters under normal constant power operation and reactivity insertion transients. Reactivity Insertion Accident (RIA) for three different initial reactivity values of 3.6, 6.0, and 6.53 mk have been simulated. The calculated peaks of the reactor power, fuel, clad and coolant temperatures in hot channel were calculated in this model. The reactor power peaks were: 103 kW at 240 s, 174 kW at 160 s and 195 kW at 140 s, respectively. The fuel temperature reached its maximum value of 116 ℃ at 240 s, 124 ℃ at 160 s and 126 ℃ at 140 s respectively. These calculation results ensured the high inherently safety features of the MNSR under all phases of the RIAs.

• Nuclear Engineering and Technology
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• 제54권2호
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• pp.764-769
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• 2022

The United Arab Emirates is currently building and operating four units of the APR-1400 developed by a South Korean vendor, Korea Electric Power Corporation (KEPCO). This paper attempts to perform APR-1400 reactor core analysis by using the well-known two-step method. The two-step method was applied to the APR-1400 first cycle using the open-source nodal diffusion code, KOMODO. In this study, the group constants were generated using CASMO-4 fuel transport lattice code. The simulation was performed in Hot Zero Power (HZP) at steady-state and transient conditions. Some typical parameters necessary for the Nuclear Design Report (NDR) were evaluated in this paper, such as effective neutron multiplication factor, control rod worth, and critical boron concentration for steady-state analysis. Other parameters such as reactivity insertion, power, and fuel temperature changes during the Reactivity Insertion Accident (RIA) simulation were evaluated as well. The results from KOMODO were verified using PARCS and SIMULATE-3 nodal core simulators. It was found that KOMODO gives an excellent agreement.

• 정보처리학회논문지C
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• 제12C권1호
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• pp.45-52
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• 2005

지식사회의 역기능인 정보시스템에 대한 각종 침해행위들로 정보자산의 피해규모는 나날이 증가하고 있다. 이러한 침해행위 중에서 네트워크 보안과 관련된 범죄수사 요구의 강화는 침해행위탐지와 이에 대한 대응 및 보고를 포함하는 다양한 형태의 침입탐지시스템들에 대한 연구개발을 촉진시켜왔다. 그러나 초기 침입탐지시스템은 설계상의 한계로 다양한 네트워크 환경에서 오탐지(false-positive)와 미탐지(false-negative)뿐만 아니라 침입탐지시스템을 우회하는 방법에 대처하기 힘들었다. 본 논문에서는 이런 문제점을 모바일 코트를 통한 최적적응 능력을 갖춘 가상프로토콜스택(Virtual Protocol Stack)을 통해 보완함으로서 침입탐지시스템이 다양한 환경에서 능동적으로 감시중인 네트워크의 상황을 자동학습 하도록 하였다. 또한 본 논문에서는 이를 적용하여 삽입/회피(Insertion/Evasion) 유형의 공격이 적극적으로 탐지될 수 있음을 보였고, 이러한 방법은 보다 다양한 혼성의 네트워크 환경에서도 적응능력을 갖춘 침입탐지 기법으로 확대 적용될 수 있음을 논의하였다.

• International Journal of Computer Science & Network Security
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• 제22권12호
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• pp.197-204
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• 2022

Sorting is an important data structure in many applications in the real world. Several sorting algorithms are currently in use for searching and other operations. Sorting algorithms rearrange the elements of an array or list based on the elements' comparison operators. The comparison operator is used in the accurate data structure to establish the new order of elements. This report analyzes and compares the time complexity and running time theoretically and experimentally of insertion, merge, and heap sort algorithms. Java language is used by the NetBeans tool to implement the code of the algorithms. The results show that when dealing with sorted elements, insertion sort has a faster running time than merge and heap algorithms. When it comes to dealing with a large number of elements, it is better to use the merge sort. For the number of comparisons for each algorithm, the insertion sort has the highest number of comparisons.

• 한국에너지공학회:학술대회논문집
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• 한국에너지공학회 1994년도 추계학술발표회 초록집
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• pp.141-145
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• 1994

A computer code for solving the 3-D time-dependent multigroup neutron diffusion equation by a coupled reactor kinetics method recently developed has been developed and for evaluating its applicability in CANDU transient analysis applied to a 3-D kinetics benchmark problem which reveals non-uniform loss of coolant accident followed by an asymmetric insertion of shutdown devices. The performance of the method and code has been compared with the CANDU design code, CERBERUS, employing a finite difference improved quasistatic method.

• Nuclear Engineering and Technology
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• 제56권2호
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• pp.359-374
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• 2024

A high-fidelity numerical analysis methodology was proposed for evaluating the fuel rod cladding integrity of a Prototype Gen IV Sodium Fast Reactor (PGSFR) during normal operation and Design basis events (DBEs). The MARS-LMR code, system transient safety analysis code, was applied to analyze the DBEs. The results of the MARS-LMR code were used as boundary condition for a 3D computational fluid dynamics (CFD) analysis. The peak temperatures considering HCFs satisfied the cladding temperature limit. The temperature and pressure distributions were calculated by ANSYS CFX code, and applied to structural analysis. Structural analysis was performed using ANSYS Mechanical code. The seismic reactivity insertion SSE accident among DBEs had the highest peak cladding temperature and the maximum stress, as the value of 87 MPa. The fuel cladding had over 40 % safety margin, and the strain was below the strain limit. Deformation behavior was elucidated for providing relative coordinate data on each active fuel rod center. Bending deformation resulted in a flower shape, and bowing bundle did not interact with the duct of fuel assemblies. Fuel rod maximum expansion was generated with highest stress. Therefore, it was concluded that the fuel rod cladding of the PGSFR has sufficient structural safety margin during DBEs.