• Nuclear Engineering and Technology
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• v.54 no.9
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• pp.3440-3447
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• 2022

The accuracy of the photoatomic cross-section data is of great importance in the field of radiation protection, particularly in the characterization of radiation shielding materials. With the release of the latest and probably the most accurate photoatomic data library, EPDL2017, the need to re-evaluate all the existing and already established mass attenuation coefficients (MACs) of all radiation shielding materials arises. The MACs of several polymers, alloy-based, glasses, and building materials used in a nuclear medicine facility were investigated using the EPDL2017 library embedded in EpiXS software and were compared to MACs available in the literature. The relative differences between MAC_EpiXS and MACXCOM were negligible, ranging from 0.02% to 0.36% for most materials. However, for material like a glass comprising of elements Te and La evaluated near their corresponding K-edge energies, the relative differences in MACs increased up to 1.46%. On the other hand, a comparison with MACs calculated based on EPDL97 (a predecessor of EPDL2017) revealed as much as a 6.61% difference. Also, it would seem that the changes in MACs were more evident in the materials composed of high atomic number elements evaluated at x-ray energies compared to materials composed of low atomic number elements evaluated at gamma-ray energies.

• Journal of Digital Convergence
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• v.11 no.12
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• pp.327-332
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• 2013

XSS is an attacker on the other party of the browser that is allowed to run the script. It is seized session of the users, or web site modulation, malicious content insertion, and phishing attack which is available. XSS attacks are stored XSS and reflected XSS. In that, two branch attacks. The form of XSS attacks are cookie sniffing, script encryption, bypass, the malignant cord diffusion, Key Logger, Mouse Sniffer, and addition of lie information addition. XSS attacks are target of attack by script language. Therefore, the countermeasure of XSS is presented and proposed to improve web security.

• Transactions of the Korean Society of Machine Tool Engineers
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• v.13 no.5
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• pp.87-95
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• 2004

From the results of AE(Acoustic Emission) source location occurred by the spot exciting as suggested in this research, it has been confirmed that AE technique is quite fruitful in figuring out the location of the occurrence, form, size and direction of the defects. As the results of examining the distribution of event for the angle of crack $\alpha$ to Xs and Ys, as the increases from $0^{\circ}$ ~ $90^{\circ}$, gradually changes its width from the axis Xs to the axis Ys. So event appears approximately similar in its size at the angle of crack $\alpha$=$45^{\circ}$, yet opposite when $\alpha$ is lager. It is believed that this is a phenomenon where its crack legnth $\alpha$, assumed as a planar defect, is to be prcjected toward the direction with a larger size. Thus, it is expected that the application of the experimental method suggested in this study would make it possible to identify the location of the defect in the material in the nondestructive way.

• Journal of the Korean Society of Surveying, Geodesy, Photogrammetry and Cartography
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• v.18 no.1
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• pp.33-40
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• 2000

The aim of this study is to extract bridge location(center line and width of a bridge) from SPOT XS data with 20. The boundary pixels were computed to get the mixture proportions of classes and this mixture proportions were used to extract center line and width of a bridge. The accuracy was tested by comparing the extracted bridge center line coordinate and width to the existing 1:5,000 scale national digital map and field survey data. The results of the comparison show that the measuring accuracy of the bridge center line coordinates and width are $\pm$2.9 m and $\pm$4.1 m.

• Nuclear Engineering and Technology
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• v.53 no.9
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• pp.2788-2802
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• 2021

Multigroup cross section (MG XS) generation by the UNIST in-house Monte Carlo (MC) code MCS for fast reactor analysis using nodal diffusion codes is reported. The feasibility of the approach is quantified for two sodium fast reactors (SFRs) specified in the OECD/NEA SFR benchmark: a 1000 MW_th metal-fueled SFR (MET-1000) and a 3600 MW_th oxide-fueled SFR (MOX-3600). The accuracy of a few-group XSs generated by MCS is verified using another MC code, Serpent 2. The neutronic steady-state whole-core problem is analyzed using MCS/RAST-K with a 24-group XS set. Various core parameters of interest (core k_eff, power profiles, and reactivity feedback coefficients) are obtained using both MCS/RAST-K and MCS. A code-to-code comparison indicates excellent agreement between the nodal diffusion solution and stochastic solution; the error in the core k_eff is less than 110 pcm, the root-mean-square error of the power profiles is within 1.0%, and the error of the reactivity feedback coefficients is within three standard deviations. Furthermore, using the super-homogenization-corrected XSs improves the prediction accuracy of the control rod worth and power profiles with all rods in. Therefore, the results demonstrate that employing the MCS MG XSs for the nodal diffusion code is feasible for high-fidelity analyses of fast reactors.

• Nuclear Engineering and Technology
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• v.53 no.3
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• pp.715-731
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• 2021

Uncertainties are calculated for pressurized water reactor (PWR) spent nuclear fuel (SNF) characteristics. The deterministic code STREAM is currently being used as an SNF analysis tool to obtain isotopic inventory, radioactivity, decay heat, neutron and gamma source strengths. The SNF analysis capability of STREAM was recently validated. However, the uncertainty analysis is yet to be conducted. To estimate the uncertainty due to nuclear data, STREAM is used to perturb nuclear cross section (XS) and resonance integral (RI) libraries produced by NJOY99. The perturbation of XS and RI involves the stochastic sampling of ENDF/B-VII.1 covariance data. To estimate the uncertainty due to modeling parameters (fuel design and irradiation history), surrogate models are built based on polynomial chaos expansion (PCE) and variance-based sensitivity indices (i.e., Sobol' indices) are employed to perform global sensitivity analysis (GSA). The calculation results indicate that uncertainty of SNF due to modeling parameters are also very important and as a result can contribute significantly to the difference of uncertainties due to nuclear data and modeling parameters. In addition, the surrogate model offers a computationally efficient approach with significantly reduced computation time, to accurately evaluate uncertainties of SNF integral characteristics.

• Nuclear Engineering and Technology
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• v.51 no.5
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• pp.1195-1208
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• 2019

This paper introduces a new two-step procedure for PWR depletion analyses. This procedure adopts the albedo-corrected parameterized equivalence constants (APEC) method to correct the lattice-based raw cross sections (XSs) and discontinuity factors (DFs) by accounting for neutron leakage. The intrinsic limitations of the conventional two-step methods are discussed by analyzing a 2-dimensional SMR with the commercial DeCART2D/MASTER code system. For a full-scope development of the APEC correction, the MASTER nodal code was modified so that the group constants can be corrected in the middle of a microscopic core depletion. The basic APEC methodology is described and color-set problems are defined to determine the APEC functions for burnup-dependent XS and DF corrections. Then the new two-step method was applied to depletion analyses of the SMR without thermal feedback, and its validity was evaluated in terms of being able to predict accurately the reactor eigenvalue and nodal power profile. In addition, four variants of the original SMR core were also analyzed for a further evaluation of the APEC-assisted depletion. In this work, several combinations of the burnup-dependent and -independent XS and DF corrections were also considered. The results show that the APEC method could enhance the nodal equivalence significantly with inexpensive additional costs.

• Proceedings of the IEEK Conference
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• 2003.07c
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• pp.2601-2604
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• 2003

원전 안전계통에 적용될 PLC는 엄격한 내진, 전자파, 내환경 시험기준을 만족해야 하며, 원전 안전등급에 부합되는 안전성 및 신뢰성을 만족해야 한다. 전 세계에서 안전계통에 적용될 PLC는 Siemens 의 Teleperm XS, Invensys 의 Triconex, WestingHouse 의 AC-160 이 있으며, 국내에서는 원전 안전계통 개발시 전적으로 이들 PLC 수입에 의존하고 있다. 현재 한국원자력연구소와 국내 PLC 제조회사간에 공동과제를 통해 안전등급 PLC 개발을 수행하고 있으며, 본 논문에서는 개발될 PLC 의 설계기준과 개발된 하드웨어 및 소프트웨어 사양 등 개발현황에 대해 기술한다.

• Proceedings of the Korean Information Science Society Conference
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• 2000.04b
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• pp.163-165
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• 2000

내용기반 이미지 검색을 위한 기존의 대부분의 기법들은 이미지 데이터에 효과적으로 적용할 수 있는 고차원의 색인구조를 고려하지 않았다. 이 연구에서는 이미지 데이터베이스에서 보다 효율적이며 정확도가 높은 검색결과를 기대할 수 있는 색상 특징 데이터 표현방법인 ECCV기법, 모양 특징 데이터 표현방법인 EPA기법을 소개한다. 또한 고차원 데이터에 대해서도 검색속도를 향상시킬 수 있는 새로운 다차원 공간 인덱스 구조인 XS-트리를 제안한다. 이 방법을 이용하면 특징표현단계에서는 차원의 수가 증가되어 저장에 필요한 공간을 많이 요구하지만 인덱싱 단계를 거치면 이미지 검색 속도가 향상되며 정확한 이미지를 검색 할 수 있는 장점이 있다.

• Broadcasting and Media Magazine
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• v.24 no.2
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• pp.73-82
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• 2019

국제 표준화 기구 ISO/IEC JCT1/SC29/WG1 JPEG(Joint Photographic Experts Group)에서는 지난 30여년간 JPEG, JPEG 2000, JPEG XR, JPEG XT, JPEG XS 등 다양한 2D 이미지 압축 관련 표준을 제정해왔다. 지난 2014년 10월에는 JPEG Pleno라는 이름으로 2D 이미지가 아닌 3차원 영상 정보 압축을 위한 새로운 표준화 과제를 시작했다. JPEG Pleno에서 다루는 3차원 영상 정보는 라이트 필드, 포인트 클라우드, 홀로그램이다. 본 원고에서는 현재 JPEG Pleno 홀로그래피에서 다뤄지는 디지털 홀로그램 영상 압축에 대한 국제 표준화 현황을 소개하고, 향후 나아갈 방향을 전망해 본다.