• 대한용접접합학회:학술대회논문집
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• 대한용접접합학회 2003년도 춘계학술발표대회 개요집
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• pp.216-218
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• 2003

A fracture mechanics analysis methodology for stress corrosion cracks (SCCs) existing in the Alloy 600 nozzle weld joint for control rod drive mechanisms (CRDMs) of pressurized water reactor is studied. Effects of weld residual stresses on the sub-critical crack behavior during the reactor operation are investigated by a fracture mechanics analysis, which is combined with the finite element alternating method. It is found that effects f the residual stresses on the stress intensity factor (SIF) and crack growth rate (CGR) are dominant and values of SIF and CGR of cracks in the region of weld joint are increased by a factor of three or more on an average.

• Nuclear Engineering and Technology
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• 제53권12호
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• pp.4003-4013
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• 2021

During the long-term cooling (LTC) phase of a loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR), water is supplied from the containment sump to the reactor coolant system (RCS) by the flooded sump water to the Reactor Vessel (RV) through the broken pipes. As part of the technical efforts for resolving GSI-191 [( Reid and Crytzer, May. 2007) 1, consideration is needed for the consequences of debris penetrating the sump screen and propagating downstream into the RV. Injection of debris (fiberglass) into the RV during the LTC recirculation phase needs special attention to assure that reactor core cooling is maintained. The point of concern is the potential for debris to adversely affect the reactor core flow paths or heat transfer [2]. However, all the experiments for proving the coolability of RV have been done with the assumption of the most of debris would be transferred to the RV and the bottom nozzle of the FAs. The purpose of the tests is to quantify the amount of the debris that would be accumulated at the lower plenum and the debris that passes through the FAs since non-conservatism of other researches assumptions that have been used in the past experimental or analytical programs.

• 대한기계학회논문집B
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• 제23권11호
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• pp.1390-1398
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• 1999

A numerical analysis for ROT sparger of PWR(Pressurized Water Reactor) is carried out. Computation is performed to investigate the flow characteristics as the change of design factor. As the result of this study, RDT sparger's flow resistance coefficient is K=3.53 at the present design condition if engineering mar&in is considered with 20%, and flow ratio into branch pipe is $Q_s/Q_i=0.41$. Velocity distribution at exit is not uniform because of separation in branch pipe. In the change of inlet flow rate and section area ratio of branch pipe for main pipe, flow resistance coefficient is increased as $Q_s/Q_i$ decreasing, but in the change of branch angle and outlet nozzle diameter of main pipe, flow resistance coefficient is decreased as $Q_s/Q_i$ decreasing. As the change rate of $Q_s/Q_i$ is the larger, the change rate of flow resistance coefficient is the larger. The change rate of pressure loss is the largest change as section area ratio changing. The optimal design condition of sparger is estimated as the outlet nozzle diameter ratio of main pipe is $D_s/D_i=0.333$, the section area ratio is $A_s/A_i=0.2$ and the branch angle is ${\alpha}=55^{\circ}$.

• Membrane and Water Treatment
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• 제10권4호
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• pp.307-311
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• 2019

The ejector type microbubble generator, which is the method to supply air to water by using cavitation in the nozzle, does not require any air supplier so it is an effective and economical. Also, the distribution of the size of bubbles is diverse. Especially, the size of bubbles is smaller than the bubbles from a conventional air diffuser and bigger than the bubbles from a pressurized dissolution type microbubble generator so it could be applied to the aeration tank for wastewater treatment. However, the performance of the ejector type microbubble generator was affected by hydraulic pressure and MLSS(Mixed Liquor Suspended Solid) concentration so many factors should be considered to apply the generator to aeration tank. Therefore, this study was performed to verify effects of hydraulic pressure and MLSS concentration on oxygen transfer of the ejector type microbubble generator. In the tests, the quantity of sucked air in the nozzle, dissolved oxygen(DO) concentration, oxygen uptake rate(OUR), oxygen transfer coefficient were measured and calculated by using experimental results. In case of the MLSS, the experiments were performed in the condition of MLSS concentration of 0, 2,000, 4,000, 8,000 mg/L. The hydraulic pressure was considered up to $2.0mH_2O$. In the results of experiments, oxygen transfer coefficient was decreased with the increase of MLSS concentration and hydraulic pressure due to the increased viscosity and density of wastewater and decreased air flow rate. Also, by using statistical analysis, when the ejector type microbubble generator was used to supply air to wasterwater, the model equation of DO concentration was suggested to predict DO concentration in wastewater.

• 한국화재소방학회논문지
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• 제33권1호
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• pp.85-91
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• 2019

이 연구는 불꽃파장 감지기술과 불꽃영상 감지기술을 융합한 도로터널용 자동소화설비의 화재감지성능을 평가하기 위한 실험이다. 화재감지성능을 향상시키기 위한 이 융합기술은 화재 시 화원의 위치를 파악하고, 노즐을 화원으로 향하여 화재가 발생한 장소에만 가압수를 방사함으로서 화재진압에 따른 수손피해를 줄이는 효과를 얻을 수 있었다. 도로터널의 화재 중 불꽃 및 연기가 선행되는 상황에서 각각 15 m, 20 m, 25 m, 30 m, 35 m 거리에 $70cm{\times}70cm$의 목표물을 두었을 때 화원의 위치를 파악하는지를 실험하였다. 실험결과 농연의 간섭으로 인해 자외선 및 삼파장적외선센서의 감지능력이 감쇠되는 결과를 확인하였다. 또한 농연으로 인해 불꽃이 가려진 경우 이미지센서가 농연을 감지하여 화재신호를 발신함을 확인하였다.

• Nuclear Engineering and Technology
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• 제49권4호
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• pp.838-849
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• 2017

This paper proposes penalty factor equations that take into consideration the weld strength over-match given in the classified form similar to the revised equations presented in the Code Case N-779 via cyclic elastic-plastic finite element analysis. It was found that the $K_e$ analysis data reflecting elastic follow-up can be consolidated by normalizing the primary-plus-secondary stress intensity ranges excluding the nonlinear thermal stress intensity component, $S_n$ to over-match degree of yield strength, $M_F$. For the effect of over-match on $K_n{\times}K_{\nu}$, dispersion of the $K_n{\times}K_{\nu}$ analysis data can be sharply reduced by dividing total stress intensity range, excluding local thermal stresses, $S_{p-lt}$ by $M_F$. Finally, the proposed equations were applied to the weld between the safe end and the piping of a pressurizer surge nozzle in pressurized water reactors in order to calculate a cumulative usage factor. The cumulative usage factor was then compared with those derived by the previous $K_e$ factor equations. The result shows that application of the proposed equations can significantly reduce conservatism of fatigue assessment using the previous $K_e$ factor equations.

• Nuclear Engineering and Technology
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• 제56권7호
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• pp.2458-2473
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• 2024

The turbulent flow in reactor pressure vessel (RPV) of pressurized water reactor (PWR) is important for the flow rate distribution at core inlet. Thus, it is vital to study the turbulent flow phenomena in RPV. However, the complicated fluid channel consisted of inner structures of RPV will block or refract the laser sheet of particle image velocimetry (PIV). In this work, the matched index of refraction (MIR) of sodium iodide (NaI) solution and acrylic was applied to support optical path for flow field measurements by PIV in the 1/10th scaled-down RPV model. The experimental results show detailed velocity field at different locations inside the scaled-down RPV model. Some interesting phenomena are obtained, including the non-negligible counterflow at the corner of nozzle edge, the high downward flowing stream in downcomer, large vortices above vortex suppression plate in lower plenum. And the intensity of counterflow and the strength of vortices increase as inlet flow rate increasing. Finally, the case of asymmetry flow was also studied. The turbulent flow has different pattern compared with the case of symmetrical inlet flow rate, which may affect the uniformity of flow distribution at the core inlet.

• 비파괴검사학회지
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• 제24권2호
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• pp.164-170
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• 2004

중수로 내부구조물 중 칼란드리아관(CT)와 액체주입노즐관(LIN)은 서로 수평으로 90도 교차되게 배열되어 있으며 원자로 내의 열, 방사선, 하중에 의해 creep 현상이 발생되어 처짐이 일어난다. 칼란드리아관은 액체주입노즐관과 동일 재료이나 운전 온도와 방사선 조사량으로 인해 액체주입노즐관에 비해 상당히 열악한 조건에 노출되어 있으므로 처짐이 심각할 것으로 예상된다. 만약 두 관의 접촉이 발생되면 원전 안전성에 영향을 미칠 것이므로 인접관에 대한 접촉여부 점검은 중수로 안전현안 중 하나이다. 이러한 접촉여부를 확인하기 위하여 핵연료채널 내부로 탐촉자를 삽입하여 인접관과의 교차점에서 간격을 직접측정하기 위한 방법으로 원거리장 와전류검사 (RFECT) 기술을 적용하였다. 핵연료채널 인접관인 액체주입노즐관 신호 취득시 발생 가능한 잡음 신호(두께변화, Lift-off, 수축)에 대해 체적적분법에 의한 모델링으로 조사하였고, 신호와 잡음과의 분리 가능한 조건을 확인하였다. 원거리장 와전류검사 적정 조건은 민감도와 투과력 그리고 잡음신호 등을 동시에 고려하여 주파수 1kHz와 코일간격 200m로서 결정하였다. 원거리장 와전류검사 실험 결과 칼란드리아관과 액체주입노즐관 사이의 간격 변화에 대한 신호 특성을 전압평면을 이용하여 상관관계를 도출하였다.

• 한국가스학회지
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• 제26권6호
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• pp.9-15
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• 2022

사용 압력 범위에서 고압 수소 탱크의 내구성을 검증하기 위해서는 수압 파열 시험이 수행되어야 한다. 그런데 물의 초기 주입 과정에서 물과 공기의 상호작용에 의해 생성된 기포가 탱크 내벽에 부착되어 잔류할 경우, 가압된 탱크가 파열되는 과정에서 기포의 급격한 압력 변화로 인해 큰 충격과 소음이 유발된다. 따라서 본 연구에서는 단순화된 수식을 통하여 탱크 내벽에 잔류하는 기포를 제거하기 위해 필요한 유속을 예측하였으며, 수소 버스용수소 용기 형상을 기준으로 해당 유속을 유지하기 위한 주입 노즐의 형상을 결정하였다. 또한 입구 압력에 따른 유속 변화를 예측하기 위하여 수치 해석 모델의 개발이 수행되었고, 예측 결과의 타당성을 입증하기 위하여 모형 제작을 통한 실험이 수행되었다. 실험 결과, 탱크 벽면 근처의 유속은 해석모델 예측 값과 유사하게 나타났으며, 입구 압력이 1.5 ~ 5.5 bar 일 경우 제거 가능한 기포의 최소 크기는 약 2.2 ~ 4.6 mm로 예측되었다.

• 대한기계학회논문집A
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• 제38권6호
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• pp.637-647
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• 2014

국내 가압경수로형 원자로의 압력용기 상부헤드에는 많은 제어봉구동장치(CRDM) 노즐이 분포한다. 이들 노즐은 억지끼워맞춤(Shrink fitting) 방식으로 결합되어 용접 처리 된다. 용접에 의해 발생되는 인장잔류응력은 일차수응력부식균열을 발생시키는 주요 요인이다. 이러한 이유로 최근 15 여 년 동안 관통노즐 용접부 부위에서 균열 발생 사례가 증가하고 있으며, 이를 극복하기 위해 다양한 방안이 모색되고 있다. 또한 용접과정에서 발생되는 불필요한 결함은 일차수응력부식균열(PWSCC)을 가속화 시키는 원인이 되기도 한다. 원자로 제작과정에서 용접에 의한 결함은 보수용접에 의해 즉시 수리가 이루어 진다. 기존의 연구에서는 정상적인 용접과정에서 발생되는 잔류응력을 예측하였으나, 본 연구에서는 용접과정에서 발생되는 결함을 보수하기 위해 실시되는 보수용접이 용접잔류응력에 미치는 영향을 분석하였다.