• Nuclear Engineering and Technology
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• 제52권4호
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• pp.776-783
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• 2020

As the refueling of a sodium-cooled fast reactor is conducted by rotating part of the reactor head without opening it, the monitoring of existing obstacles that can disturb the rotation of the reactor head is one of the most important issues. This paper deals with the ultrasonic ranging technique that directly monitors the existence of possible obstacles located in a lateral gap between the upper internal structure and the reactor core in a prototype generation IV sodium-cooled fast reactor (PGSFR). A 10 m long plate-type ultrasonic waveguide sensor, whose feasibility has been successfully demonstrated through preliminary tests, was employed for the ultrasonic ranging technique. The design of the sensor's wave radiating section was modified to improve the radiation performance, and the radiated field was investigated through beam profile measurements. A test facility simulating the lower part of the upper internal structure and the upper part of the reactor core with the same shapes and sizes as those in the PGSFR was newly constructed. Several under-water performance tests were then carried out at room temperature to investigate the applicability of the developed ranging technique using the plate-type ultrasonic waveguide sensor with the actual geometry of the PGSFR's internal structures.

• 비파괴검사학회지
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• 제26권6호
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• pp.440-446
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• 2006

The reactor vessel body and closure head are fastened with the stud bolt that is one of crucial parts for safety of the reactor vessels in nuclear power plants. It is reported that the stud bolt is often experienced by fatigue cracks initiated at threads. Stud bolts are inspected by the ultrasonic technique during the overhaul periodically for the prevention of failure which leads to radioactive leakage from the nuclear reactor. The conventional ultrasonic inspection for stud bolts was mainly conducted by reflected echo method based on shadow effect. However, in this technique, there were numerous spurious signals reflected from every oblique surfaces of the thread. In this study, ultrasonic phased array technique was applied to investigate detectability of flaws in stud bolts and characteristics of ultrasonic images corresponding to different scanning methods, that is, sector and linear scan. For this purpose, simplified stud bolt specimens with artificial defects of various depths were prepared.

• 비파괴검사학회지
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• 제25권6호
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• pp.439-445
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• 2005

The stud bolt is one of crucial parts for safe operation of reactor vessels in nuclear power plants, Crack initiation and propagation were reported in stud bolts that arc used for closure of reactor vessel and head, Stud bolts are inspected by ultrasonic technique during overhaul periodically for the prevention of stud bolt failure which could induce radioactive leakage from nuclear reactor, In conventional ultrasonic testing for inspection of stud bolts, cracks are detected by using shadow effect It takes too much time to inspect stud bolts by using conventional ultrasonic technique. In addition, there were numerous spurious signals reflected from every oblique surfaces of thread, In this study, the signal processing technique for enhancing conventional ultrasonic technique was introduced for inspecting stud bolts. The signal processing technique provides removing spurious signal reflected from every oblique surfaces of thread and enhances detectability of defects. Detectability for small crack was enhanced by using this signal processing in ultrasonic inspection of stud bolts in Nuclear Power Plants.

• 한국안전학회지
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• 제8권3호
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• pp.56-63
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• 1993

In this study the ultrasound which has the properties of mixing, surface cleaning effect, increasing of the effective reaction surface area and increasing of the effective collision frequency, was used to enhance the recovering efficiency of Cu from the Cu-ion containning waste water. The ultrasonic reactor used in this study was dsigned and constructed for improving the disadvantage of the existing ultrasonic reactor From the experimental result and its analysis. we obtained following conclusions. 1. The ultrasound increased the rate of electrochemical deposition to 582.2% in maximum at the Condition of 0.1M-CuSO$_4$and 2.1V-overpotential. 2. This study gave the possibility of the scale-up of ultrasonic reactor and In particular, ultrasonic reactor would be effective in treatment of waste water contains a low concentration of Cu ion.

• 자원리싸이클링
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• 제3권3호
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• pp.32-49
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• 1994

포항제철소에서 발생되는 석회석슬러지의 기본탄산계 특성중의 일부분인 수화반응 연구를 수행하여 다음과 같은 결과를 얻었다. 1. 석회석슬러지는 광물조성상 calcite이며 고품위(CaO 51%) 미분말(15~22$\mu\textrm{m}$) 석회석으로 보통탄산칼슘 영역 (-3mm + 325mesh)에 속하는 것으로 분류되었다. 2. 석회석슬러지는 수세슬러지와 소성로 습식집진 dust의 혼합슬러지이며 약 8:2의 비율로 구성되어 있다. 수차례 시료채취한 소성로 습식집진 dust는 전형적인 calciteduTdmsk 실조업에서는 일부 열분해 시작한 quick lime과 다시 집진수와 수화된 slaked lime의 혼재가 예상되므로 두 공정 슬러지의 분리로 석회석슬러지의 품위를 향상시킬 수 있다. 3. 석회석슬러지를 소성, 수화하여 제조된 slaked lime의 각종 수화반응기 종류별에 변화에 대해 검토하였다. 일반적인 기계적인 교반기인 magnetic stirrer의 shaking incubator, ultrasonic vibration reactor을 비교 검토한 결과 ultrasonic vibration reactor에서 격렬하지 않은 수화반응과 타반응기 보다 미세한 분체생성 및 균일한 입도분포의 특징을 갖고 있었다. 4. Ultrasonic vibration reactor에서 미분말의 slaked limetod성에 최적인 광액 농도는 10wt%이하였으며, 수화완료 시간도 5~10분으로 타반응기 보다 짧았다. 5. 석회석슬러지는 천연산 석회석을 원료로 한 경우 10~20$\mu\textrm{m}$의 불균질 slaked lime 분체를 생성에 반해 석회석슬러지는 균일한 1~5$\mu\textrm{m}$ 분체를 생성하였다.

• 한국압력기기공학회 논문집
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• 제10권1호
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• pp.44-50
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• 2014

There were many flaw issues of reactor vessel head penetration in USA fleets. USNRC issued 10CFR50.55a to implement reactor vessel head penetration ultrasonic examination performance demonstration(PD) in US for enhancement of inspection reliability. After September 2009, all US utilities inspected their RVHP with PD qualified system. Korea Hydro and Nuclear Power Company(KHNP) have developed reactor vessel head penetration performance demonstration system for ultrasonic test to apply for pressurized light-water reactor power plants in accordance with 10CFR50.55a since September 2011. RVHP configuration surveying and analysis, code requirement analysis, and performance demonstration specimen design were performed up to this day. Fingerprinting of manufactured specimen, development of test data management program, development of operation procedure, input of flawed data, and development of final report will be performed for the next step. This paper describes the development status of the performance demonstration system for reactor vessel head penetration ultrasonic examination in Korea.

• 한국유체기계학회 논문집
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• 제6권1호
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• pp.57-65
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• 2003

The measurement uncertainties of an ultrasonic flowmeter were analyzed to evaluate its applicability to the measurement of the steam generator feedwater flow-rate in a nuclear power plant. The analyses of measurement uncertainties of a reactor power were also performed with the analyses of feedwater flow measurement uncertainties. Two ultrasonic flowmeters based on a cross-correlation technique and a transit time method were used in this study. The ultrasonic flowmeters were installed on a feedwater pipe line of a typical 1000 MWe Korea-standardized nuclear power plant to take the necessary data. The results have shown that the measurement uncertainties of the ultrasonic flowmeters are adequately smaller than those or a venturi meter. The research has also indicated that the measurement uncertainties of the reactor power based on the ultrasonic flowmeter uncertainties are sufficiently bounded by the uncertainty range usually assumed in nuclear safety analyses.

• Nuclear Engineering and Technology
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• 제56권2호
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• pp.437-443
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• 2024

The development and testing of inspection equipment is necessary for the safe deployment of advanced nuclear reactors. One proposed advanced reactor design is Westinghouse's lead-cooled fast reactor (LFR). In this paper, the process of achieving adequate wetting for an ultrasonic under-lead viewing system is discussed and results presented. Such a device would be used for inspection in the molten lead core during reactor outages. Wider tests into the wetting of various materials in molten lead at microscale were performed using electron microscopy. The possible mechanisms and kinetics for materials wetting in lead, particularly stainless steel and nickel, are proposed and discussed.

• 비파괴검사학회지
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• 제21권3호
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• pp.307-312
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• 2001

운전중인 원자로 재료의 건전성 평가를 위한 기계적 시험의 하나인 샤르피 충격 시험편에 대하여 초음파 신호분석이 이루어졌나 시험편으로는 모재와 용접재를 사용하였는데 이들 재료는 고온, 고압의 냉각수 및 지속적인 고속중성자가 방출되고 있는 가동중인 발전소에서 감시시험을 통한 원자로재료의 건전성평가를 목적으로 정지기간동안 인출된 깃이다. 분석결과 속도 및 감쇠와 같은 초음파 특성들이 재질이 비교적 균일한 모재에 있어서는 중성자 조사량과 밀접한 관련이 있는 것으로 보였으며 이를 활용하여 비파괴적인 방법으로 재료에 대한 중성자 조사량이 어느 정도인지를 예측할 수 있는 가능성을 보여주었다.

• 한국소음진동공학회논문집
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• 제25권1호
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• pp.48-57
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• 2015

제 4세대 원자로로 개발되고 있는 소듐냉각고속로는 냉각재로 사용되는 소듐의 물과 공기에 의한 반응을 방지하기 위하여 원자로 헤드의 개방 없이 회전 구동만을 이용하여 핵연료 교환을 수행한다. 따라서 핵연료 교환을 위해서는 노심과 상부내부구조물 사이의 공간에 원자로 헤드의 회전 구동을 방해하는 장애물의 존재 여부를 확인하는 검사가 반드시 선행되어야 하는데, 소듐의 불투명성으로 인해 통상적인 광학 장비를 사용한 검사방법으로는 장애물의 확인이 어렵고, 초음파를 이용한 검사방법이 적용되어야 한다. 이 연구에서는 불투명한 소듐 중에서 노심과 상부내부구조물 사이의 장애물 존재 여부를 확인하기 위하여 판형 웨이브가이드 초음파 센서를 적용한 원격주사 검사기법을 개발하였다. 웨이브가이드 센서는 원자로헤드 상부의 저온 구간에 초음파 트랜스듀서를 설치하고 길이가 긴 웨이브가이드를 사용하여 노심 상부의 고온 고방사능 소듐 내부로 초음파를 전파시키기 때문에, 고온 고방사능에 의한 손상 없이 장시간 적용이 가능한 장점을 가지고 있다. 먼저, 수평 방향으로 초음파를 방사시킬 수 있는 10 m 길이의 수평 빔 웨이브가이드 센서를 설계 제작하였고, 제작된 센서의 특성 분석을 위한 빔 프로파일 측정 및 기초 실험을 수행하여 방사되는 초음파의 빔 폭과 전파 거리를 평가하였다. 또한, 실제 장애물로 작용할 수 있는 부품들의 형상인 원형 목표물에 대한 원격탐지 성능시험을 수행하여 개발된 원격주사 기술의 유용성을 평가하였다.