• Nuclear Engineering and Technology
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• 제55권4호
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• pp.1310-1323
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• 2023

A reactor coolant pump (RCP) is essential for transporting coolant in the primary loop of pressurized water reactors. In the advanced passive reactor, the absence of a long pipeline between the steam generator and RCP serves as a transition section, resulting in a non-uniform flow field at the pump inlet. Therefore, the characteristics of the pump should be investigated under non-uniform flow to determine its influence on the pump. In this study, the pressure pulsation characteristics were examined in the time and frequency domains, and the sources of low-frequency and high-amplitude signals were analyzed using wavelet coherence analysis and numerical simulation. From computational fluid dynamics (CFD) results, non-uniform inflow has a great effect on the flow structures in the pump's inlet. The pressure pulsation in the pump at the rated flow increased by 78-128.7% under the non-uniform inflow condition in comparison with that observed under the uniform inflow condition. Furthermore, a low-frequency signal with a high amplitude was observed, whose energy increased significantly under non-uniform flow. The wavelet coherence and CFD analysis verified that the source of this signal was the low-frequency pulsating vortex under the steam generator.

• 한국물환경학회지
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• 제25권6호
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• pp.896-901
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• 2009

In this study, in order to apply the air and pure oxygen in the Jet Loop Reactor (JLB) in which the oxygen transfer rate is high, differentiate the operation mode according to each air flowrate and liquid flowrate and investigate the oxygen transfer characteristic, an experiment was carried out. The oxygen concentration with the air flowrate ($Q_g$) and liquid flowrate ($Q_L$) was identical but the oxygen transfer coefficient ($K_L{\cdot}a$) is linear depending on degree of two factors. The width of an increase is small in $0.1min^{-1}$ when the air flowrate is 0.2 L/min with increasing the liquid flowrate. Whereas, the increment was exposed to be very high for $1.5min^{-1}$ when the air flowrate was 5 L/min. In the experiments using the pure oxygen, it was 30 mg/L of oxygen concentration finally and it was 3.5 times than using the air. But the time reached the saturated concentration was similar to using the air, and $K_L{\cdot}a$ was similar to using the air too. Analysis between two independent variable and oxygen transfer of the correlation is the same model like $K_L{\cdot}a={0.0161Q_L}^{1.5371}{Q_g}^{0.5433}$ using with coefficient non linear regression analysis. It was resulted that the liquid flowrate were approximately three times than air flowrate on effect to oxygen transfer rate.

• 대한기계학회논문집A
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• 제33권2호
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• pp.179-184
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• 2009

The Fuel Test Loop(FTL) which is capable of an irradiation testing under a similar operating condition to those of PWR(Pressurized Water Reactor) and CANDU(CANadian Deuterium Uranium reactor) nuclear power plants has been developed and installed in HANARO, KAERI(Korea Atomic Energy Research Institute). It consists of In-Pile Section(IPS) and Out-of Pile System(OPS). The IPS, which is located inside the pool is divided into 3-parts; the in-pool pipes, the IVA(IPS Vessel Assembly) and the support structures. The test fuel is loaded inside a double wall, inner pressure vessel and outer pressure vessel, to keep the functionality of the reactor coolant pressure boundary. The IVA is manufactured by local company and the functional test and verification were done through pressure drop, vibration, hydraulic and leakage tests. The brazing technique for the instrument lines has been checked for its functionality and performance. An IVA has been manufactured by local technique and have finally tested under high temperature and high pressure. The IVA and piping did not experience leakage, as we have checked the piping, flanges, assembly parts. We have obtained good data during the three cycle test which includes a pressure test, pressure and temperature cycling, and constant temperature.

• Korean Chemical Engineering Research
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• 제58권4호
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• pp.665-674
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• 2020

외부순환형 공기부양반응기에서 낮은 주파수의 압력 변동에 대해 연구하였다. 상승관과 하강관의 상부와 하부에 설치된 내압관의 액면을 휴대폰으로 촬영하는 방법으로 빠른 주파수의 변동이 제거된 압력을 측정하였다. 자기상관함수와 교차상관함수의 계산을 통해 압력의 주기적인 변동을 확인하였다. 기체속도가 일정하여도 순환액체의 관성으로 인해 압력은 물론이고 상승관과 하강관내의 기체체류량도 주기적으로 변동하였다. 일반적으로 기체유속이 증가할수록 압력 변동의 강도는 커졌다. 비분산 액체높이가 0.04 m일 때 압력 변동의 주기는 기체속도가 0.14 ms^-1에서 극대값을 보여주었다. 이는 기체속도가 커질수록 순환 액체속도의 증가율은 둔화하고 효과적으로 순환하는 액체의 부피가 감소하므로 순환액체의 관성이 극대값을 보이기 때문이다.

• 에너지공학
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• 제25권4호
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• pp.85-92
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• 2016

초고온가스로는 열출력 밀도가 낮아 노심용융의 가능성이 낮으며, 냉각재 상실사고 시 수소 발생 등으로 인한 폭발의 위험도 없다. 안전성 측면의 장점과 더불어 냉각재를 초고온으로 만들어 전력생산이외에 산업시설용 공정열로의 응용도 가능하다. 본 논문에서는 초고온가스로를 일차계통으로 하고, 전력 및 공정열 공급이 가능한 이차계통의 개념 설계를 담고 있다. 기존에 NGNP(Next Generation Nuclear Part)에서 제안한 350 MW 열출력 원자로 모델을 기반으로 수소생산 루프와는 별도로 전력생산을 위한 300 MW의 열에너지를 중간열교환기를 통해 이차계통으로 전달하는 참조모델을 개발하고, 이를 열역학적 측면에서 분석하였으며 이차계통 각 지점에서 주요 설계변수에 따른 효율분석과 최적화개념 연구를 수행하였다.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집A
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• pp.636-643
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• 2001

Interference between the crossover leg of the reactor coolant system (RCS) and the pipe whip restraints (PWR) has brought a degradation issue of the integrity of the Reactor Coolant System in Westinghouse type nuclear power plants (NPPs) of Korea. According to the gap Inspect ion carried out during planned overhaul (Year 2000), interference between the crossover leg and the PWR was found in each RCS loop. This plant has had the high vibration problem on the RC pump 'B'. The reason for the high vibration in the RC pump 'B' had been massively surveyed and it was found that the crossover leg of RCS contacted with the PWR in hot condition. Since the contact between the crossover leg and the PWR changes the dynamic characteristics of the piping system for the RCS, this is considered as one reason for the high vibration. And a possibility of overstress on the crossover leg due to the contact with the PWR should be evaluated. Through performing RCS integrity analyses, subsequent actions were initiated to increase the gap between those parts. As the results of the appropriate separation between two parts, it was reported that there was no unusual noise or vibration during plant heat-up. In this paper, the evaluations for the gap between the crossover leg and the PWR and the structural integrity due to loop binding is described.

• 대한기계학회논문집A
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• 제37권5호
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• pp.665-671
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• 2013

제 4 세대 소듐냉각 고속로에는 중간열교환기(IHX), 붕괴열제거 열교환기(DHX), 공기 열교환기(AHX), 핀형 소듐-공기 열교환기(FHX) 및 증기발생기(SG)를 포함한 다양한 열교환기들이 설치된다. 본 연구에서는 STELLA-1 시험루프에 설치된 소듐-공기 열교환기인 AHX 와 SELFA 시험루프에 설치될 핀형(finned) 소듐-공기 열교환기인 FHX 등 2 기의 열교환기 설계에 대해 3D 상세 유한요소해석을 수행하고, 동 결과에 기초하여 고온설계 기술기준을 따라 크리프-피로 손상평가를 수행하였다. 손상 평가결과 AHX와 FHX는 의도하는 크리프 피로 손상 하중 하에서 구조 건전성을 유지하는 것으로 확인되었다.

• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2789-2802
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• 2020

Small Modular Reactors (SMRs) are attracting wide attention due to their outstanding performance, extensive studies have been carried out for lead-based fast reactors (LFRs) that cooled with Lead or Lead-bismuth (LBE), and small modular natural circulation LFR is one of the promising candidates for SMRs and LFRs development. One of the challenges for the design small modular natural circulation LFR is to master the natural circulation thermal-hydraulic performance in the reactor primary circuit, while the natural circulation characteristics is a coupled thermal-hydraulic problem of the core thermal power, the primary loop layout and the operating state of secondary cooling system etc. Thus, accurate predicting the natural circulation LFRs thermal-hydraulic features are highly required for conducting reactor operating condition evaluate and Thermal hydraulic design optimization. In this study, a thermal-hydraulic analysis code is developed for small modular natural circulation LFRs, which is based on several mathematical models for natural circulation originally. A small modular natural circulation LBE cooled fast reactor named URANUS developed by Korea is chosen to assess the code's capability. Comparisons are performed to demonstrate the accuracy of the code by the calculation results of MARS, and the key thermal-hydraulic parameters agree fairly well with the MARS ones. As a typical application case, steady-state analyses were conducted to have an assessment of thermal-hydraulic behavior under nominal condition, and several parameters affecting natural circulation were evaluated. What's more, two characteristics parameters that used to analyze natural circulation LFRs natural circulation capacity were established. The analyses show that the core thermal power, thermal center difference and flow resistance is the main factors affecting the reactor natural circulation. Improving the core thermal power, increasing the thermal center difference and decreasing the flow resistance can significantly increase the reactor mass flow rate. Characteristics parameters can be used to quickly evaluate the natural circulation capacity of natural circulation LFR under normal operating conditions.

• 대한기계학회논문집A
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• 제34권9호
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• pp.1241-1248
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• 2010

초고온가스로에서 생성된 $950^{\circ}C$ 정도의 초고온 열을 이용하여 수소를 경제적이며 또한 대량으로 생산하기 위한 시스템이 원자력수소생산시스템이며, 공정열교환기는 초고온 열과 황-요오드 공정을 통해 수소를 생산하는 원자력수소생산시스템에서의 핵심 기기이다. 한국원자력연구원에서는 초고온가스로에 사용될 기기에 대한 성능시험을 위해 최대 작동 설계온도 $1000^{\circ}C$인 헬륨가스루프를 구축하고 있으며 공정열교환기를 설계하였다. 본 연구에서는 구축중인 헬륨가스루프에서 성능시험을 수행할 예정으로 설계된 공정열교환기에 대한 고온 구조건전성을 미리 평가하기 위한 작업의 일환으로 고온구조해석 모델링, 열해석 및 열팽창 해석을 수행한 결과를 정리한 것이다. 해석결과를 이용하여 설계된 공정열교환기의 구조건전성을 유지하기 위한 1 차 및 2 차 열매체의 유입/유출 파이프라인에서의 적절한 구속조건을 결정하였으며 이를 향후 제작될 공정열교환기 시제품의 성능시험 장치 설계에 반영할 것이다.

• 청정기술
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• 제23권2호
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• pp.205-212
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• 2017

본 연구에서는 합성폐수로부터 암모니아 탈기 시 이유체 벤츄리형 선회 노즐이 장착된 제트 루프 반응기의 성능을 평가하고자 하였다. 이를 위해 이유체 벤츄리형 선회 노즐과 일반 노즐이 장착된 각각의 제트 루프 반응기를 이용하여 조업조건 변화에 따른 암모니아 제거효율과 총괄물질전달계수($K_La$)를 각각 얻은 후, 이를 통해 성능을 비교하였다. 운전변수로는 pH(pH = 10-12), 액체순환유량($Q_L=25-35L\;min^{-1}$), 공기유입량($Q_G=5-20L\;min^{-1}$)을 변화시키며 실험하였다. 실험결과, 동일한 조업조건에서 이유체 벤츄리형 선회 노즐(two-fluid venturi-type swirl nozzle, TVSN)이 장착된 제트 루프 반응기가 이유체 벤츄리형 일반 노즐(two-fluid venturi-type conventional nozzle, TVCN)이 장착된 제트 루프 반응기보다 암모니아 제거효율과 $K_La$가 높게 나타났다. 이와 같은 결과는 이유체 벤츄리형 선회 노즐이 장착된 제트 루프 반응기에서 형성된 선회류 흐름에 의해 난류강도가 이유체 벤츄리형 일반 노즐이 장착된 제트 루프 반응기에 비해 높기 때문이라 판단된다. 또한, 실험조건 범위에서 $K_La$는 pH, 공기유입량 및 액체순환유량이 증가할수록 증가하는 경향을 보였으며, 특히, 실험변수 중 공기유입량이 pH나 액체순환유량에 비해 $K_La$에 미치는 영향이 큰 것으로 나타났다.