• 정보과학회 컴퓨팅의 실제 논문지
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• 제20권11호
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• pp.610-614
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• 2014

많은 과학 데이타처럼 화산재 확산 시뮬레이션 결과는 NetCDF 형식의 군집화된 희소행렬이다. 그리고 크기가 커서 저장과 전송에 많은 비용이 발생한다. 본 논문에서는 다차원 인덱스를 일차원으로 바꾸고 연속된 0을 그 시작점과 길이만을 기록하여 화산재 확산 시뮬레이션 데이터의 크기를 줄이는 방법을 제안한다. 이 방법은 기존의 ZIP 형식으로 압축한 것과 거의 같은 성능을 보이나 NetCDF의 구조는 손상하지 않는다. 제안된 방법에 의하면 데이터 크기가 줄어들어 저장공간의 효율이 높아지고 네트워크 전송시간이 줄어드는 효과를 기대할 수 있을 것이라 사료된다.

• 한국환경과학회지
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• 제27권8호
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• pp.723-735
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• 2018

In this study, to investigate an optimal configuration method for the modeling system, we performed an optimization experiment by controlling the types of compilers and libraries, and the number of CPU cores because it was important to provide reliable model data very quickly for the national air quality forecast. We were made up the optimization experiment of twelve according to compilers (PGI and Intel), MPIs (mvapich-2.0, mvapich-2.2, and mpich-3.2) and NetCDF (NetCDF-3.6.3 and NetCDF-4.1.3) and performed wall clock time measurement for the WRF and CMAQ models based on the built computing resources. In the result of the experiment according to the compiler and library type, the performance of the WRF (30 min 30 s) and CMAQ (47 min 22 s) was best when the combination of Intel complier, mavapich-2.0, and NetCDF-3.6.3 was applied. Additionally, in a result of optimization by the number of CPU cores, the WRF model was best performed with 140 cores (five calculation servers), and the CMAQ model with 120 cores (five calculation servers). While the WRF model demonstrated obvious differences depending on the number of CPU cores rather than the types of compilers and libraries, CMAQ model demonstrated the biggest differences on the combination of compilers and libraries.

• 한국컴퓨터정보학회:학술대회논문집
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• 한국컴퓨터정보학회 2015년도 제52차 하계학술대회논문집 23권2호
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• pp.99-100
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• 2015

본 논문에서는 해양현상의 하나인 와동류를 컴퓨터 환경에서 모의하는 방안에 대해 제안한다. 이를 위해 와동류의 구조적 특징을 분석하고 이와 유사하게 모의하는 방안을 소개한다. 또한 해양 분야에서 가장 널리 사용되는 netCDF 포맷의 실 수온데이터를 이용하여 와동류를 표현하고 NASA에서 제공하는 공개 분석 툴을 이용하여 결과를 비교 분석한다. 또한 모의한 와동류가 실제 해양전투 모의실험에서 어떻게 활용 될 수 있는지 그 활용방안에 대해 소개한다.

• Nuclear Engineering and Technology
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• 제50권8호
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• pp.1372-1386
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• 2018

Despite recent advances in multi-hazard analysis, the complexity and inherent nature of such problems make quantification of the landslide effect in a probabilistic safety assessment (PSA) of NPPs challenging. Therefore, in this paper, a practical approach was presented for performing an earthquake-induced landslide PSA for NPPs subject to seismic hazard. To demonstrate the effectiveness of the proposed approach, it was applied to Korean typical NPP in Korea as a numerical example. The assessment result revealed the quantitative probabilistic effects of peripheral slope failure and subsequent run-out effect on the risk of core damage frequency (CDF) of a NPP during the earthquake event. Parametric studies were conducted to demonstrate how parameters for slope, and physical relation between the slope and NPP, changed the CDF risk of the NPP. Finally, based on these results, the effective strategies were suggested to mitigate the CDF risk to the NPP resulting from the vulnerabilities inherent in adjacent slopes. The proposed approach can be expected to provide an effective framework for performing the earthquake-induced landslide PSA and decision support to increase NPP safety.

• 한국농림기상학회지
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• 제22권3호
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• pp.152-163
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• 2020

실제적인 산사태 대응조치 단계 이전에 산사태위험지수를 통하여 산사태 발생 위험도를 모니터링하고 예측하기 위하여, LAMP의 고해상도 강우와 토양수분 예측 자료를 DB화 하고, 산사태 연구자들의 연구대상 지역에 적합한 지도 투영법과 공간해상도로 변환하는 절차를 ArcGIS를 이용하여 마련하였다. 이를 위하여 ERA5 재분석 강수와 농촌진흥청 10m 깊이 토양수분자료를 이용하여 LAMP 모델 강수 및 토양수분 자료를 정량적 그리고 정성적으로 평가하여 모델의 특성을 파악하였다. 또한, LAMP 강우, 토양수분, 증발산 등의 결과 자료를 10m 초고해상도 ArcGIS 포맷 자료로 변환하는 과정을 실무적으로 상세히 기술하여, 국내 지역에서 WRF 모델의 NetCDF 자료를 ArcGIS로 이용자들이 손쉽게 변환할 수 있도록 기술적 편의를 제공하였다.

• Nuclear Engineering and Technology
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• 제39권3호
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• pp.215-220
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• 2007

The existing flooding Probabilistic Safety Analysis(PSA) was updated to reflect the Korean plant specific operating experience data into the flooding frequency to improve the PSA quality. Both the Nuclear Power Experience(NPE) database and the Korea Nuclear Pipe Failure Database(NuPIPE) databases were used in this study, and from these databases, only the Pressurized Water Reactor(PWR) data were used for the flooding frequencies of the flooding areas in the primary auxiliary building. With these databases and a Bayesian method, the flooding frequencies for the flooding areas were estimated. Subsequently, the Core Damage Frequency(CDF) for the flooding PSA of the Ulchin(UCN) unit 3 and 4 plants based on the Korean Standard Nuclear Power Plant(KSNP) internal full-power PSA model was recalculated. The evaluation results showed that sixteen flooding events are potentially significant according to the screening criterion, while there were two flooding events exceeding the screening criterion of the existing UCN 3 and 4 flooding PSA. The result was compared with two kinds of cases: (1) the flooding frequency and CDF from the method of the existing flooding PSA with the PWR and Boiled Water Reactor(BWR) data of the NPE database and the Maximum Likelihood Estimate(MLE) method and (2) the flooding frequency and CDF with the NPE database(PWR and BWR data), NuPIPE database, and a Bayesian method. From the comparison, a difference in CDF results was revealed more clearly between the CDF from this study and case (2) than between case (1) and case (2). That is, the number of flooding events exceeding the screen criterion further increased when only the PWR data were used for the primary auxiliary building than when the Korean specific data were used.

• 한국수자원학회:학술대회논문집
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• 한국수자원학회 2016년도 학술발표회
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• pp.233-233
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• 2016

현재 한국건설기술연구원에서 X-밴드 이중편파레이더를 운영하고 있으며, 이 결과 NetCDF 파일형식의 레이더 관측자료가 생성되고 있다. 레이더 자료포맷인 Netcdf 자료의 경우 레이더 관측과정에서 발생한 결과를 극좌표 형식으로 저장하고 있어 이를 분석이나 시스템에 적용하여 활용하기 위해서는 격자좌표로 변환하는 것이 필요하고, 또한 다양한 자료 변환 및 추출작업을 텍스트 기반으로 하기 위해 다양한 사전 작업이 필요하여 일반사용자가 사용하는데 어려운 상황이다. 그래서 이를 쉽게 수행할 수 있도록 JAVA를 이용하여 윈도우 기반으로 사용할 수 있는 프로그램(KICTRadar4WIN) 프로그램을 개발하였다. KICTRadar4WIN 프로그램의 경우 레이더 자료 품질관리, 레이더 자료 관리, 레이더 자료 추출, 레이더 자료 표출의 4가지 기능을 포함하고 있다. ${\bullet}$ 레이더 자료 품질관리 - 원시자료에 QC 기준을 입력하여 QC된 레이더자료를 생성 ${\bullet}$ 레이더 자료관리 - CAPPI 자료생성 : 관측된 PPI 및 RHI 자료를 이용하여, CAPPI 자료를 생성 - QPE 자료생성 : CAPPI 자료를 이용하여 QPE 자료를 생 - QPE 자료보정 : 지점우량을 이용한 G/R비를 산정하여 QPE 보정자료를 생성 ${\bullet}$ 레이더 자료 추출 - 격자자료 추출 : PPI, CAPPI, QPE 자료를 TEXT 자료로 변환하여 저장 - 지점자료 추출 : 입력된 지점좌표 중심으로 선택한 범위의 평균값을 TEXT 파일로 저장 - 면적자료 추출 : 입력된 면적자료의 평균값을 추출하여 TEXT파일로 저장 ${\bullet}$ 레이더 자료 표출 - 영상표출 : PPI, CAPPI, QPE 관측변수 자료를 그림파일 생성 - KMZ 자료생성 : PPI, CAPPI, QPE 자료를 KMZ 파일 생성

• Nuclear Engineering and Technology
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• 제54권9호
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• pp.3324-3335
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• 2022

Several countries show interest in the Generation-IV power reactor innovative small module (PRISM), including: Canada, Japan, Korea, Saudi Arabia and the United Kingdom. Generation IV International Forum (GIF) has recommended the utilizing of probabilistic safety assessment (PSA) in evaluating the safety of Generation-IV reactors. This paper reviews the PSA performed for PRISM using SAPHIRE 7.27 code. This work shows that the core damage frequency (CDF) of PRISM for a single module is estimated by 8.5E-8/year which is lower than the Generation-IV target that is 1E-6 core damage per year. The social risk of PRISM (likelihood of latent cancer fatality) with evacuation is estimated by 9.0E-12/year which is much lower than the basic safety objective (BSO) that is 1E-7/year. The social risk without evacuation is estimated by 1.2E- 11/year which is also much lower than the BSO. For the individual risk (likelihood of prompt fatality), it is concluded that it can be considered negligible with evacuation (1.0E-13/year). Assuming no evacuation, the individual risk is 2.7E-10/year which is again much lower than the BSO. In comparison with other PSAs performed for similar sodium fast reactors (SFRs), it shows that PRISM concept has the lowest CDF.

• Nuclear Engineering and Technology
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• 제50권8호
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• pp.1210-1216
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• 2018

Site or multi-unit (MU) risk assessment has been a major issue in the field of nuclear safety study since the Fukushima accident in 2011. There have been few methods or experiences for MU risk assessment because the Fukushima accident was the first real MU accident and before the accident, there was little expectation of the possibility that an MU accident will occur. In addition to the lack of experience of MU risk assessment, since an MU nuclear power plant site is usually very complex to analyze as a whole, it was considered that a systematic method such as probabilistic safety assessment (PSA) is difficult to apply to MU risk assessment. This paper proposes a new MU risk assessment methodology by using the conventional PSA methodology which is widely used in nuclear power plant risk assessment. The logical failure structure of a site with multiple units is suggested from the definition of site risk, and a decomposition method is applied to identify specific MU failure scenarios.

• Nuclear Engineering and Technology
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• 제54권1호
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• pp.110-116
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• 2022

Human failure event (HFE) dependency analysis is a part of human reliability analysis (HRA). For efficient HFE dependency analysis, a maximum number of minimal cut sets (MCSs) that have HFE combinations are generated from the fault trees for the probabilistic safety assessment (PSA) of nuclear power plants (NPPs). After collecting potential HFE combinations, dependency levels of subsequent HFEs on the preceding HFEs in each MCS are analyzed and assigned as conditional probabilities. Then, HFE recovery is performed to reflect these conditional probabilities in MCSs by modifying MCSs. Inappropriate HFE dependency analysis and HFE recovery might lead to an inaccurate core damage frequency (CDF). Using the above process, HFE recovery is performed on MCSs that are generated with a non-zero truncation limit, where many MCSs that have HFE combinations are truncated. As a result, the resultant CDF might be underestimated. In this paper, a new method is suggested to incorporate HFE recovery into the MCS generation stage. Compared to the current approach with a separate HFE recovery after MCS generation, this new method can (1) reduce the total time and burden for MCS generation and HFE recovery, (2) prevent the truncation of MCSs that have dependent HFEs, and (3) avoid CDF underestimation. This new method is a simple but very effective means of performing MCS generation and HFE recovery simultaneously and improving CDF accuracy. The effectiveness and strength of the new method are clearly demonstrated and discussed with fault trees and HFE combinations that have joint probabilities.