• 한국통신학회논문지
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• 제14권6호
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• pp.590-603
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• 1989

본 논문에서는 단축 Hamming 부호의 일종이며 오류검출용 검사비트 수가 16인 CRC-CCITT 부호화 원시다항식 CRC 부호에 대한 성능 분석을 위하여 필수적으로 요구되는 중분포(weight distribution)를 구하는 기법과 오류검출 성능을 분석하는 기법을 제안하였고, 두 CRC(cyclic redundant code)부호를 CCITT에서 광대역 ISDN의 가입자망 인터페이스의 전송방식으로 권고된 ATM(asynchronous transfer mode)전송방식의 오류검출을 부호로 적용하여 현재 고려되고 있는 cell 크기에 대한 증분포 및 미검출오류확률(undetected error probability)을 구한 후, 두 오류검출부호의 성능을 비교/분석 하였다. 분석 결과, 현재 고려되는 셀 크기에 대해 CRC-CCITT 부호의 성능이 원시다항식 CRC 부호의 성능보다 더 우수함이 입증되었다 .이를 위한 모든 계산을 IBM PC/AT를 이용하여 수행하였다. 한편 본 논문에서 제안한 단축 Hamming 부호의 성능 분석 기법은 지금까지 디지틀 통신시스템에 적용되고 있는 또는 적용예정인 CRC 오류검출 부호의 성능 분석에 이용될 수 있다.

• Nuclear Engineering and Technology
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• 제52권7호
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• pp.1347-1354
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• 2020

To improve the efficiency of MC criticality calculation, an acceleration method of fission source convergence which gives an improved initial fission source is proposed. In this method, the MC global homogenization is carried out to obtain the macroscopic cross section of each material mesh, and then the nonlinear iterative solution of the SP3 equations is used to determine the fission source distribution. The calculated fission source is very close to the real fission source, which describes its space and energy distribution. This method is an automatic computation process and is tested by the C5G7 benchmark, the results show that this acceleration method is helpful to reduce the inactive cycles and overall running time.

• 천문학논총
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• 제24권1호
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• pp.43-51
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• 2009

이 연구에서는 임의의 밀도 분포를 갖는 성간 먼지 구름에 의해 산란되는 산란광을 분석할 수 있는 몬테카를로 시뮬레이션 코드를 개발하였다. 개발된 코드의 신뢰성을 확보하기 위해 구 대칭의 성간먼지 구름의 중심에 별이 있고, 별빛이 얼마만큼 산란되어 나오는 지 계산하여 Code (1973)의 결과와 비교하였으며, Code의 근사식과 매우 잘 일치하는 결과를 주는 것을 확인하였다. 이 코드는 우리 은하뿐만 아니라 외부은하의 경우에도 손 쉽게 확장이 가능하다. 개발된 코드는 과학위성 1호로 관측된 원자외선 연속복사광의 분석에 적용하여 성간먼지 구름의 특성과 우리 은하의 복사장의 분포를 연구하는 데 사용하고자 한다.

• Journal of Information Processing Systems
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• 제15권1호
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• pp.100-115
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• 2019

Malicious code distribution on the Internet is one of the most critical Internet-based threats and distribution technology has evolved to bypass detection systems. As a new defense against the detection bypass technology of malicious attackers, this study proposes the automated tracing of malicious websites in a malware distribution network (MDN). The proposed technology extracts automated links and classifies websites into malicious and normal websites based on link structure. Even if attackers use a new distribution technology, website classification is possible as long as the connections are established through automated links. The use of a real web-browser and proxy server enables an adequate response to attackers' perception of analysis environments and evasion technology and prevents analysis environments from being infected by malicious code. The validity and accuracy of the proposed method for classification are verified using 20,000 links, 10,000 each from normal and malicious websites.

• Nuclear Engineering and Technology
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• 제52권3호
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• pp.477-484
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• 2020

The control rod drive mechanism needs to be debugged after reactor fresh fuel loading. It is of great importance to monitor the subcriticality of this process accurately. A modified method was applied to the subcriticality monitoring process, in which only a single control rod cluster was fully withdrawn from the core. In order to correct the error in the results obtained by Neutron Source Multiplication Method, which is based on one point reactor model, Monte Carlo neutron transport code was employed to calculate the fission neutron distribution, the iterated fission probability and the neutron flux in the neutron detector. This article analyzed the effect of a coarse mesh and a fine mesh to tally fission neutron distributions, the iterated fission probability distributions and to calculate correction factors. The subcriticality before and after modification is compared with the subcriticality calculated by MCNP code. The modified results turn out to be closer to calculation. It's feasible to implement the modified NSM method in large local reactivity addition process using Monte Carlo code based on 3D model.

• 한국해양공학회지
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• 제10권2호
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• pp.13-19
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• 1996

For fatigue analsis of offshore structures, existing methods have been reviewed and a computer code has been developed on PC. As methods to estimate the probabillity distribution of the fatigue stress, three methods(the deterministic method, the stochastic method, and the simplified method) are used in this code, to choose the appropriate method according to the situations. This code estimates damage ratios, fatigue lives, and probabilities of fatigue failure considering scatterness of SN-data, based on linear damage rule and SN-curves. Also, allowable stress for the design extreme wave can calculated by the simplified method.

• 천문학논총
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• 제14권1호
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• pp.23-32
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• 1999

We have developed a Monte Carlo code, which solves the problem of radiative transfer in anisotropically scattering atmosphere. The radiative code is flexible in handlings of the system geometry, the distribution of scattering particles, and the source-particle geometry. This code treats the case of highly forward throwing scattering. As performance tests, we have compared the result of Monte Carlo calculations with that of Quasi-Diffusion method for a spherically symmetric cloud model.

• 한국수학교육학회지시리즈E:수학교육논문집
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• 제6권
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• pp.371-381
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• 1997

Let p be an odd prime number. We introduce simple and useful decoding algorithm for orthogonal Latin square codes of order p. Let H be the parity check matrix of orthogonal Latin square code. For any x ${\in}$ GF(p)$^{n}$, we call xH$^{T}$ the syndrome of x. This method is based on the syndrome decoding for linear codes. In L$_{p}$, we need to find the first and the second coordinates of codeword in order to correct the errored received vector.

• Nuclear Engineering and Technology
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• 제55권8호
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• pp.2785-2796
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• 2023

How to generate the precise broad group cross section is important for the fast reactor design. In this study, a fast reactor multi-group cross-section generation code MGGC2.0 are developed in-house for processing ultrafine group MATXS format library. Validation and verification are performed for MGGC2.0 code by applying the benchmarks of ICSBEP handbook, and the results of MGGC2.0 agree well with that of MCNP. The consistent P_N method with critical buckling search is in good agreement that condensed with TWODANT flux and flux moment for the inner core and outer core region. For the radial blanket and reflector, two region approximation method has been applied in MGGC2.0 by using collision Probability Method neutron flux solver. The RBEC-M benchmark was used to verify the power distribution calculation, and the relative error of power distribution comparison with the reference are less than 0.8% in the fuel region and the maximum relative error is 5.58% in the reflector region. Therefore, the precise broad cross section can be generated by MGGC2.0 for fast reactor.

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1204-1212
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• 2024

To accurately calculate the heating distribution of the fast reactor, a neutron-photon library in MATXS format named Knight-B7.1-1968n × 94γ was processed based on the ENDF/B-VII.1 library for ultrafine groups. The neutron cross-section processing code MGGC2.0 was used to generate few-group neutron cross sections in ISOTXS format. Additionally, the self-developed photon cross-section processing code NGAMMA was utilized to generate photon libraries for neutron-photon coupled heating calculations, including photo-atom cross sections for the ISOTXS format, prompt photon production cross sections, and kinetic energy release in materials (KERMA) factors for neutrons and photons, and the self-shielding effect from the capture and fission cross sections of neutron to photon have been taken into account when the photon source generated by neutron is calculated. The interface code GSORCAL was developed to generate the photon source distribution and interface with the DIF3D code to calculate the neutron-photon coupling heating distribution of the fast reactor core. The neutron-photon coupled heating calculation route was verified using the ZPPR-9 benchmark and the RBEC-M benchmark, and the results of the coupled heating calculations were analyzed in comparison with those obtained from the Monte Carlo code MCNP. The calculations show that the library was accurately processed, and the results of the fast reactor neutron-photon coupled heating calculations agree well with those obtained from MCNP.