• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.450-451
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• 2005

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.514-515
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• 2005

• Nuclear Engineering and Technology
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• 제51권8호
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• pp.1939-1950
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• 2019

The MELCOR code useful for a plant-specific hydrogen risk analysis has inevitable limitations in prediction of a turbulent flow of a hydrogen mixture. To investigate the accuracy of the hydrogen risk analysis by the MELCOR code, results for the turbulent gas behavior at pipe rupture accident were compared with CFX results which were verified by the American National Standard Institute (ANSI) model. The postulated accident scenario was selected to be surge line failure induced by station blackout of an Optimized Power Reactor 1000 MWe (OPR1000). When the surge line failure occurred, the flow out of the surgeline was strongly turbulent, from which the MELCOR code predicted that a substantial amount of hydrogen could be released. Nevertheless, the results indicated nonflammable mixtures owing to the high steam concentration released before the failure. On the other hand, the CFX code solving the three-dimensional fluid dynamics by incorporating the turbulence closure model predicted that the flammable area continuously existed at the jet interface even in the rising hydrogen mixtures. In conclusion, this study confirmed that the MELCOR code, which has limitations in turbulence analysis, could underestimate the existence of local combustible gas at pipe rupture accident. This clear comparison between two codes can contribute to establishing a guideline for computational hydrogen risk analysis.

• Nuclear Engineering and Technology
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• 제43권2호
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• pp.187-194
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• 2011

Korea Nuclear Fuel is developing the X-GEN fuel which shows high performance and robust reliability for the worldwide supply. However, the simplified code systems such as CESEC-III which were developed in 1970s are still used in the current Non-LOCA safety analysis of OPR1000 and APR1400 plants. Therefore, it is essential to secure an advanced safety analysis methodology to make the best use of the merits of X-GEN fuel. To accomplish this purpose, the $\b{i}$ntegrated $\b{s}$afety $\b{a}$nalysis $\b{m}$ethodology (iSAM), is developed by selecting the best-estimate thermal-hydraulic code RETRAN. iSAM possesses remarkable advantages, such as generality, integrity, and designer-friendly features. That is, iSAM can be applied to both OPR1000 and APR1400 plants and uses only one computer code, RETRAN, in the whole scope of the non-LOCA safety analyses. Also the iSAM adopts the unique and automatic initialization and run tool, $\b{a}$utomatic $\b{s}$teady-$\b{s}$tate $\b{i}$nitialization and $\b{s}$afety analysis too l (ASSIST), to enable unhandy designers to use the new design code RETRAN without difficulty. In this paper, a brief overview of the iSAM is given, and the results of applying the iSAM to typical non-LOCA transients being checked during the reload design are reported. The typical non-LOCA transients selected are the single control element assembly withdrawal (SCEAW) accident, the asymmetric steam generator transients (ASGT), the locked rotor (LR) accident, and bank CEA withdrawal (BCEAW) event. Comparison to current licensing results shows a close resemblance; thus, it reveals that the iSAM can be applied to the non-LOCA safety analysis of OPR1000 and APR1400 plants.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2012년도 추계학술대회 논문집
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• pp.145-146
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• 2012

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.577-578
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• 2005

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.496-497
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• 2005

• 한국문헌정보학회지
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• 제57권2호
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• pp.79-96
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• 2023

본 연구는 대표적인 OPR(Open Peer Review) 플랫폼인 F1000Research에서 사회과학분야의 논문 585건을 대상으로 개방형 동료 심사 결과를 분석하고 피인용, 알트메트릭스와 어떠한 관련성을 보이는지 확인하였다. 더불어 논문의 활용이 피인용에 미치는 영향 관계 내에서 심사 점수가 조절효과(Moderating effect)를 나타내는지 검증함으로써, OPR 환경에서 고품질로 평가된 논문이 피인용을 촉진할 수 있는지 확인하였다. 분석 결과 첫 번째, 승인과 조건부 승인된 논문 그룹 간에 피인용 횟수에 유의미한 차이가 나타나지 않았지만, 환산된 심사 점수와 피인용 횟수는 유의한 정(+)의 상관성(r= 0.40 ~ 0.60)을 나타냈다. 두번째, 심사 점수는 알트메트릭스와도 약한 상관성을 나타내 심사자의 품질 평가 결과는 피인용과 사회적 영향을 약하게 예측할 수 있는 것으로 분석되었다. 마지막으로 심사 점수는 논문의 활용을 피인용으로 이어지게 하는데 유의한 양의 방향의 조절효과 (B=1.69, P < 0.01)를 수행하며, 조건부 효과 검사 결과 가장 고품질로 평가된 논문 집단에서 가장 큰 효과(B=11.32, 95% CI [10.57, 12.08])를 나타내는 것으로 검증되었다. 따라서 공개된 심사 결과는 연구자들의 우수 논문 선별을 도와 인용을 유도하는데 도움을 줄 수 있는 것으로 파악되었다.

• 한국소음진동공학회논문집
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• 제23권4호
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• pp.308-314
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• 2013

The vibration and stress analysis program of comprehensive vibration assessment program(CVAP) is to theoretically verify the structural integrity of reactor vessel internals(RVI) and to provide the basis for selecting the locations monitored in measurement and inspection programs. This paper covers the applicability of the vibration and stress analysis method of APR1400 RVI CVAP. The analysis method was developed to use 3-dimensional detail hydraulic and structural models with ANSYS and CFX. To assess the method, the hydraulic loads and structural reponses of OPR1000 were predicted and compared with the measured data in the OPR1000 RVI CVAP. The results predicted with this method were close to the measured values considerably. Therefore, the analysis method was developed properly.

• 한국산학기술학회논문지
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• 제14권4호
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• pp.2043-2048
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• 2013

원자력발전소 OPR-1000 CE형 증기발생기는 전열관 재질이 Alloy-600 HTMA으로 되어 있고, 2차측은 퇴적된 슬러지로 인해 ODSCC가 발생한다. ODSCC는 관판 주변에 집중되고 있고, 슬러지 높이에 따라 영향을 받고 있다. 증기발생기 2차측 부식분위기 저감과 함께 전열관의 응력부식균열의 발생을 억제하기 위하여 부분화학세정을 실시하였다. 슬러지 제거량은 259.2kg이고, 퇴적 슬러지 높이는 0.71인치에서 0.34인치로 낮아졌으며, 부식율은 최대 2.34mils로서 EPRI 권고사항인 10mils 이내로 만족하였다.