• Nuclear Engineering and Technology
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• 제52권11호
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• pp.2638-2651
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• 2020

Nozzle corner cracks present at the intersection of reactor pressure vessels (RPVs) and inlet or outlet nozzles have been a persistent problem for a number of years. The fracture analysis of such nozzle corner cracks is very important and critical for the efficient design and assessment of the structural integrity of RPVs. This paper aims to perform an engineering critical assessment of RPVs with nozzle corner cracks subjected to several transients accompanied by pressurized thermal shocks. The critical crack size of the RPV model with nozzle corner cracks under transient loading is evaluated on failure assessment curve. In particular, the influence of cladding on the crack initiation of nozzle corner crack under thermal transients is studied. The influence of primary internal pressure and secondary thermal stress on the stress field at nozzle corner and SIF at crack front is analyzed. Finally, the influence of different crack size and crack shape on the final critical crack size is analyzed.

• Nuclear Engineering and Technology
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• 제54권1호
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• pp.401-413
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• 2022

This paper provides a simple method by which to estimate the cross-section stress profiles for nozzles designed according to ASME Code Section III. Further, this method validates the effectiveness of earlier work performed by the authors on standard nozzles. The method requires only the geometric information of the pressure vessel and the attached nozzle. A PWR direct vessel injection nozzle, a PWR outlet nozzle, a PWR inlet nozzle and a BWR recirculation outlet nozzle are selected based on their corresponding specific designs, e.g., a varying nozzle radius, a varying nozzle thickness and an outlet nozzle boss. A cross-section stress profile comparison shows that the estimates are in good agreement with the finite element analysis results. Differences in stress intensity factors calculated in accordance with ASME BPVC Section XI Appendix G are discussed. In addition, a change in the dimensions of an alternate nozzle design relative to the standard values is discussed, focusing on the stress concentration factors of the nozzle inside corner.

• 한국가시화정보학회지
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• 제9권2호
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• pp.48-53
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• 2011

The shape of nozzle cross-section plays an important role in stabilizing electrospray jet. The angle of contact line is governed based on the famous Young-Laplace equation. Compared to a round nozzle that has a constant curvature along the orifice, the square nozzle has four square corner edges and four straight edges that hold the meniscus in a different manner and is of interest in this study. By utilizing both square and round capillary nozzle, we examine the effect of nozzle shape in electrohydrodynamic jetting. The ejections were recorded with a high speed camera and analyzed to examine the jetting repeatability based on dynamic movement of meniscus. The result suggests that if the corner edges are not sharp, then its effect on repeatability is also limited.

• Nuclear Engineering and Technology
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• 제54권5호
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• pp.1726-1746
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• 2022

This paper presents fracture mechanics analysis results for various cracks located at pressurized water reactor pressure vessel nozzle crotch corners taking into consideration constraint effect. Technical documents such as the ASME B&PV Code, Sec.XI were reviewed and then a fracture mechanics analysis procedure was proposed for structural integrity assessment of various nozzle crotch corner cracks under normal operation conditions considering the constraint effect. Linear elastic fracture mechanics analysis was performed by conducting finite element analysis with the proposed analysis procedure. Based on the evaluation results, elastic-plastic fracture mechanics analysis taking into account the constraint effect was performed only for the axial surface crack of the reactor pressure vessel outlet nozzle with cladding. The fracture mechanics analysis result shows that only the axial surface crack in the reactor pressure vessel outlet nozzle has the stress intensity factor exceeding the low bound of upper-shelf fracture toughness irrespectively of considering the constraint effect. It is confirmed that the J-integral for the axial crack of the outlet nozzle does not exceed the ductile crack initiation toughness. Hence, it can be ensured that the structural integrity of all the cracks is maintained during the normal operation.

• Nuclear Engineering and Technology
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• 제54권6호
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• pp.2188-2197
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• 2022

To ensure the safety margin of a reactor pressure vessel (RPV) under normal operating conditions, it is regulated through the pressure-temperature (P-T) limit curve. The stress intensity factor (SIF) obtained by the internal pressure and thermal load should be obtained through crack analysis of the nozzle corner crack in advance to generate the P-T limit curve for the nozzle. In the ASME code Section XI, Appendix G, the SIF via the internal pressure for the nozzle corner crack is expressed as a function of the cooling or heating rate, and the wall thickness, however, the SIF via the thermal load is presented as a polynomial format based on the stress linearization analysis results. Inevitably, the SIF can only be obtained through finite element (FE) analysis. In this paper, simple prediction equations of the SIF via the thermal load under, cool-down and heat-up conditions are presented. For the Korean standard nuclear power plant, three geometric variables were set and 72 cases of RPV models were made, and then the heat transfer analysis and thermal stress analysis were performed sequentially. Based on the FE results, simple engineering solutions predicting the value of thermal SIF under cool-down and heat-up conditions are suggested.

• 한국가시화정보학회지
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• 제13권3호
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• pp.29-34
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• 2015

The interaction between a normal shock wave and a boundary layer along a wall surface in internal compressible flows causes a very complicated flow. This interaction region containing shock train and mixing region is called as pseudo-shock waves. Pseudo-shock waves in the divergent part of a rectangular nozzle have been investigated by using large-eddy simulation (LES). LES studies have been done for the complex flow phenomena of three-dimensional pseudo-shock waves. The LES results have been validated against experimental wall-pressure measurements. The LES results are in good agreement with experimental results. Pseudo-shock length and corner separation have been studied in three-dimensional LES model. Comparison of centerline pressure measurement and 3D visualization measurement has been discussed for the corner separation position. It has been concluded that the pseudo-shock length should be measured by using 3D visualization measurement.

• 한국화재소방학회논문지
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• 제26권2호
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• pp.53-58
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• 2012

본 연구에서는 가연성 물질을 고려한 워터커튼 시스템(Water Curtain System)의 열 및 연기유동 제어 특성을 실험적으로 분석하였다. 이를 위해서 Room Corner Tester(RCT)를 사용하여 연료의 종류가 소나무(PineWood)와 가솔린(Gasoline)인 경우 각각의 발열량(Heat Release Rate)을 구하였으며, 워터커튼용 화재실험 장치를 제작하여 화원근방에서 5m 떨어진 지점의 천장 부근에 분사각도 $180^{\circ}$, 오리피스 직경 8.2 mm의 노즐(Nozzle)을 설치한 후 목재와 가솔린 각각에 대해서 화재실험을 실시하여 워터커튼 전후의 온도분포와 가시도를 측정하였다. 그결과 워터커튼 시스템의열및연기유동 제어는 가연성 물질의 연소특성에 따른 고온의 연기발생량과 분사 노즐에 의한 유동현상이 중요한 상관관계를 갖고 있음을 확인하였다.

• Nuclear Engineering and Technology
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• 제56권6호
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• pp.2292-2306
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• 2024

This study addresses cracks and fracture problems in engineering structures that may cause significant challenges and safety concerns, with a focus on pressure vessels in nuclear power plants. Comprehensive parametric three-dimensional mixed mode fracture analyses for inclined and deflected nozzle corner cracks with various crack shape aspect ratios and depth ratios in nuclear reactor pressure vessels are carried out. Stress intensity factor (SIF) solutions are obtained using FRAC3D, which is part of Fracture and Crack Propagation Analysis System (FCPAS), employing enriched finite elements along the crack front. Also, improved empirical equations are developed to allow the determination of mixed mode SIFs, K_I, K_II, and K_III, for any values of the parameters considered in the study. This study provides practical solutions to assess the remaining life and fail-safe conditions of nuclear reactors by providing accurate SIF determination.

• 대한기계학회논문집B
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• 제38권3호
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• pp.235-242
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• 2014

공기 베어링의 성능개선을 위하여, 일반적인 급기공 형상(drill shape), 곡면 급기공 형상(matched cube shape) 및 $45^{\circ}C$ 모따기 노즐 출구부(trimmed shape)를 가지는 3가지 형태의 노즐형상에서 급기압을 변화 시켰을 때, 샤프트면 출구압력 특성을 전산유체역학 상용코드를 이용하여 분석하였다. 샤프트면 에서 압력 분포는 노즐 중심부에서 정체점 유동의 영향으로 최대압이 발생하며, 노즐 출구부와 샤프트면 사이의 압력분포는 미세 간극의 영향으로 와류가 형성되어 반경방향으로 국부적인 압력상승 현상이 발생한 후 음압영역이 발생하는 것이 관찰되었다. 또한 이러한 현상은 일반적인 형태의 노즐에서 급기압력비 6.92이상인 경우는 나타나지 않는 것으로 관찰되었다. 급기공 노즐 형상을 matched cubic 곡면으로 변화시켜 샤프트면에서 얻어진 압력 분포는 기존의 노즐과 비교한 결과 순간적인 상승압 구간이 모든 경우에 대하여 존재하였으며 급기압력비 10근처까지 음압구간이 나타나는 것으로 관찰되었다. 또한, 노즐 출구부를 모따기로 변형시켰을 때, 샤프트면에서 최대압력의 영향권이 반경방향으로 확대되었고 음압영역은 나타나지 않는 것으로 관찰되었다. 결과적으로, 급기공 내부의 형상변화보다는 노즐 출구면 외부의 변형이 성능개선에 유리한 것으로 관찰된다.

• 대한기계학회논문집B
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• 제36권3호
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• pp.233-240
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• 2012

레이저 절단가공에서 사용되는 보조가스의 충돌특성을 개선하기 위한 실험적 연구가 진행되었다. 보조가스의 압력, 노즐의 위치 및 각도 등 다양한 관계변수의 변화에 대하여, 초음속 사각노즐에서 분출되는 보조가스의 절단면 충돌특성이 기존의 원형노즐 경우와 비교 관찰되었다. 이를 위하여 쉴러린 유동가시화 및 절단면 하단에서의 피토압 측정이 진행되었다. 본 연구에서 응용된 사각노즐은 절단면 모서리에서 발생하는 마하디스크의 강도를 줄이고, 이를 통하여 기존의 원형노즐에 비하여 절단면을 따라 흐르는 보조가스의 박리현상을 약화시키고 보조가스 후방의 피토압력을 증가시킬 수 있음이 확인되었다.