• Nuclear Engineering and Technology
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• 제41권6호
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• pp.821-830
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• 2009

In this paper, modal testing and finite element modeling results to identify the modal parameters of a nuclear fuel rod as well as its cladding tube are discussed. A vertically standing full-size cladding tube and a fuel rod with lead pellets were used in the modal testing. As excessive flow-induced vibration causes a failure in fuel rods, such as fretting wear, the vibration level of fuel rods should be low enough to prevent failure of these components. Because vibration amplitude can be estimated based on the modal parameters, the dynamic characteristics must be determined during the design process. Therefore, finite element models are developed based on the test results. The effect of a lumped mass attached to a cladding tube model was identified during the finite element model optimization process. Unlike a cladding tube model, the density of a fuel rod with pellets cannot be determined in a straightforward manner because pellets do not move in the same phase with the cladding tube motion. The density of a fuel rod with lead pellets was determined by comparing natural frequency ratio between the cladding tube and the rod. Thus, an improved fuel rod finite element model was developed based on the updated cladding tube model and an estimated fuel rod density considering the lead pellets. It is shown that the entire pellet mass does not contribute to the fuel rod dynamics; rather, they are only partially responsible for the fuel rod dynamic behavior.

• Nuclear Engineering and Technology
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• 제53권10호
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• pp.3236-3246
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• 2021

Lessons learned from the Fukushima Daiichi nuclear power plant accident directed that multiple failures should be considered more seriously rather than single failure in the licensing bases and safety cases because attempts to take accident management measures could be unsuccessful under the high radiation environment aggravated by multiple failures, such as complete loss of electric power, uncontrollable loss of coolant inventory, failure of essential safety function recovery. In the case of the complete loss of electric power called station blackout (SBO), if there is no mitigation action for recovering safety functions, the reactor core would be overheated, and severe fuel damage could be anticipated due to the failure of the active heat sink. In such a transient condition at CANDU-6 plants, the seal failure of the primary heat transport (PHT) pumps can facilitate a consequent increase in the fuel sheath temperature and eventually lead to degradation of the fuel integrity. Therefore, it is necessary to specify the regulatory guidelines for multiple failures on a licensing basis so that licensees should prepare the accident management measures to prevent or mitigate accident conditions. In order to explore the efficiency of implementing accident management strategies for CANDU-6 plants, this study proposed a realistic accident analysis approach on the SBO transient with multiple-failure sequences such as seal failure of PHT pumps without operator's recovery actions. In this regard, a comparative study for two PHT pump seal failure modes with and without coolant seal leakage was conducted using a best-estimate code to precisely investigate the behaviors of thermal-hydraulic parameters during transient conditions. Moreover, a sensitivity analysis for different PHT pump seal leakage rates was also carried out to examine the effect of leakage rate on the system responses. This study is expected to provide the technical bases to the accident management strategy for unmitigated transient conditions with multiple failures.

• 한국전산구조공학회논문집
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• 제18권4호통권70호
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• pp.347-360
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• 2005

경수로 원자로 하부구조물에서 발생되는 유포의 불균일성에 기인하는 교차류와 핵연료집합체의 수력저항의 차이에 의해 발생하는 교차류, 그리고 축류 등에 의해 유발되는 연료봉의 불안정성은 핵연료손상의 원인이 될 수 있으므로, 새로운 연료 개발 시 연료봉에 대한 진동 및 안정성 해석을 수행하여 연료봉 진동과 불안정성 발생 여부를 확인하고 있다. 본 연구에서는 새로 개발된 고리 2호기용 $16{\times}16$형 개량핵연료 집합체에 대한 연료봉의 진동 및 안정성 해석을 수행하여 지지격자 높이와 위치, 그리고 지지조건 등이 연료봉의 진동특성 및 안정성에 미치는 영향을 평가하였다 그리고 해석결과에 근거하여 개량연료 집합체에서 중간지지격자 높이와 각 지지격자의 위치를 제안하였다.

• 한국가스학회지
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• 제16권3호
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• pp.48-53
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• 2012

이 논문의 목적은 LPG 자동차의 액상 분사시스템에 관련된 고장사례를 연구하는 것이다. LPi 분사시스템인 인젝터를 점검한 결과, 인젝터에 카본이 누적되어 운전 중에 간헐적으로 연료를 분사하는 인젝터의 미세한 홀을 막아 연비를 5% 정도 떨어뜨리는 것으로 확인되었다. 엔진의 공회전을 조절하는 시스템인 공회전 조절장치 부품과 엔진에 공기를 공급하는 시스템인 스로틀 보디에 카본이 퇴적되어 공기의 흐름을 간섭함으로써 연비가 7% 악화된 것을 확인되었다. 엔진의 흡기 매니폴드 개스킷의 일부가 찢어져, 실린더 헤드와 실린더 블록의 밀착성이 약화되어 흡기행정에서 외부의 공기가 이 틈새로 간헐적으로 유입되면서 증가된 공기량만큼 연료량의 증가를 가져와 엔진의 회전수가 증가하여 부조화 현상이 발생되어 정상적인 상태보다 연비가 3% 정도 악화된 것으로 확인되었다. 이러한 고장사례는 운전중에 엔진의 출력 성능을 떨어뜨리고, 자동차의 연비를 악화시키는 요인이 된다. 따라서 품질확보에 철저하게 대처하여 고장현상을 최소화 하여야 할 것으로 판단된다.

• Nuclear Engineering and Technology
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• 제35권2호
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• pp.144-153
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• 2003

The object of this paper is the probabilistic failure analysis on the cladding performance of WPF(Whole Pin Furnace) test fuel pins under transient conditions, and analysis of the KALIMER fuel pin using the preceding analysis. The cumulative damage estimation and Weibull probability estimation of WPF test are performed. The probabilistic method was adapted for these analyses to determine the effective thickness thinning due to eutectic penetration depth. In the results, it is difficult to assume that a brittle layer depth made by eutectic reaction is all of the thickness reduction due to cladding thinning. About 93% cladding thinning of the eutectic penetration depth is favorable as an effective thickness of cladding. And the unreliability of the KALIMER driver fuel pin under the same WPF test condition is lower than that of the WPF pin because of the higher plenum-fuel volume ratio and lower cladding inner radius vs. thickness ratio. KALIMER fuel pin developed from conceptual design has a more stable transient performance for a failure mechanism due to fission gas buildup than the WPF pin.

• 방사성폐기물학회지
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• 제11권1호
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• pp.31-39
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• 2013

핵연료는 원자로 운전 중 예기치 못한 상황에서 연료 결함을 초래할 수 있다. 핵연료 결함은 연료봉의 수소화나 이물질에 의한 금속 마모, 그리고 펠렛과 피복관의 상호작용에 의해 피복관이 손상된다. 이렇게 손상된 핵연료의 결함원인을 규명하는 것은 원자력발전의 안전운전에 중요하다고 사료된다. 핵연료가 손상되면 원자로 냉각재가 오염되어 원자로 출력을 낮추거나, 발전소를 정지할 수도 있다. 모든 사용후연료는 건식저장고로 이동 보관되어야 하나, 결함연료는 이동할 수 없으므로 이 연구의 목적은 중수로형 원자로에서 연료가 인출된 후 사용후연료 저장조에서 보관된 연료에 대하여 결함 여부를 판단할 수 있는 기술을 개발하고자 하였다. 이 연구를 통하여 핵종 누설 검출 기술을 이용한 사용후연료 검사기술을 개발하였으며, 이 기술을 월성발전소에 적용함으로써, 검사기술 및 검사시스템에 대한 성능을 입증하였다.

• 한국항공운항학회지
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• 제17권1호
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• pp.24-28
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• 2009

The reliability assessment is performed for Pressure Control Regulator of Aircraft Fuel System using reliability procedure which consists of the reliability analysis and the Failure Modes and Effects Analysis(FMEA). The target reliability as MTBF(Mean Time Between Failure) is set to 5000hr. During the reliability analysis process, the system is categorized by Work Breakdown Structure(WBS) up to level 3, and a reliability structure is defined by schematics of the system. Since the components and parts that have been collected through EPRD/NPRD. The predicted reliability to meet mission requirements and operating conditions is estimated as 4375.9hr. To accomplish the target reliability, the components and parts with high RPN have been identified and changed by analyzing the potential failure modes and effects. By changing the configuration design of components and parts with high-risk, the design is satisfied target reliability.

• Nuclear Engineering and Technology
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• 제30권3호
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• pp.262-272
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• 1998

The experiences and causes of pressure tube cracking accidents in the CANDU reactors and the development of the fuel channel at AECL(Atomic Energy Canada Limited) have been described. Most of the accidents were caused by Delayed Hydride Cracking(DHC). In the cases of the Pickering units 3&4 and the Bruce unit 2, excessive residual stresses induced by an improper rolled joint process played a role in DHC. In the Pickering unit 2, cracks formed by contact between the pressure and calandria tubes due to the movement of the garter spring were the direct cause of the failure. To extend the life of a fuel channel, several R&D programs examining each component of the fuel channel have been carried out in Canada. For a pressure tube, the main concern is focused on changing the fabrication processes, e.g., increasing cold working rate, conducting intermediate annealing and adding a third element like Fe, V, and Cr to the tube material. In addition to them, chromium plating on the end fitting and increasing wall thickness at both ends of the calandria tube are considered. There has also been much interest in the improvement of fuel channel performance in our country and several development programs are currently under way.

• 한국기계가공학회지
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• 제17권5호
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• pp.97-102
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• 2018

Combat vehicles require high levels of maneuverability, firepower, armor, and operability. A high-performance power system is required for optimal maneuverability. The fuel pump which supplies fuel stably is very important to achieve this. The fuel pump consists of a pump part, a motor part, and a control part. It is equipped with a BLDC motor. Numerous failures of the fuel pump occurred during vehicle operation when exposed to vibration, shock, and high temperature. The cause of failure was confirmed to be stator slip of the BLDC motor. Stator slip is a consequence of the interference loss between the stator and the housing of the motor part in an high temperature environment. The failure of the fuel pump was solved through size control of the motor housing and the stator. We performed vibration testing at high temperature for verification. This study contributes to improving the reliability of combat vehicles.

• 대한기계학회논문집A
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• 제41권5호
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• pp.375-380
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• 2017

본 논문은 한국원자력연구원에서 개발 중인 소듐냉각 고속로 핵연료의 연료봉 하단 마개에 있는 관통구멍과 마운팅 레일의 원기둥 형상과의 접촉부에 발생하는 접촉 손상을 예측하기 위한 가속시험 방법을 연구한 것이다. 가속시험 조건으로서 연료봉의 유체유발진동수 및 진폭을 유한요소 해석을 통하여 구하였다. 약 35000 시간의 연료봉 수명기간을 고려한 가속시험 시간을 결정하기 위해 일반 기계부품류의 신뢰성 평가 방법을 적용하였으며, 이때 가장 보수적인 형상 모수와 원자로 내에서의 연료봉 파손허용 개수 기준 및 연료봉 피복관 재료인 HT-9강의 피로수명 데이터를 이용하였다. 시편의 개수를 5개로 하였을 때, 최종적으로 계산된 가속 시험시간은 각 시편 당 16.5시간이었다. 가속시험 후 전체 시편에 어떠한 접촉손상도 관찰되지 않을 때 연료봉의 수명기간 중 $B_{0.004}$ 수명이 신뢰수준 99%로 보장되는 것으로 평가하였다.