• Title/Summary/Keyword: On-power Inspection

Search Result 544, Processing Time 0.042 seconds

A New Approach to Selection of Inspection Items using Risk Insight of Probabilistic Safety Assessment for Nuclear Power Plants

  • Park, Younwon;Kim, Hyungjin;Lim, Jihan;Choi, Seongsoo
    • Transactions of the Korean Society of Pressure Vessels and Piping
    • /
    • v.14 no.2
    • /
    • pp.49-58
    • /
    • 2018
  • The regulatory periodic inspection program (PSI) conducted at every overhaul period is the most important process for confirming the safety of nuclear power plants. The PSI for operating nuclear power plants in Korea mainly consist of component level performance check that had been developed based on deterministic approach putting the same degree of importance to all the inspection items. This inspection methodology is likely to be effective for preoperational inspection. However, once the plant is put into service, the PSI must be focused on whether to minimize the risk of accident using defense-in-depth concept and risk insight. The incorporation of defense-in-depth concept and risk insight into the deterministic based safety inspection has not been well studied so far. In this study, two track approaches are proposed to make sure that core damage be avoided: one is to secure success path and the other to block the failure path in a specific event tree of PSA. The investigation shows how to select safety important components and how to set up inspection group to ensure that core damage would not occur for a given initiating event, which results in strengthening defense-in-depth level 3.

A Mobile Robot for Nuclear Power Plant Applications

  • Kim, Chang-Hoi;Seo, Yong-Chil;Cho, Jai-Wan;Choi, Young-Soo;Kim, Seung-Ho
    • 제어로봇시스템학회:학술대회논문집
    • /
    • 2003.10a
    • /
    • pp.803-807
    • /
    • 2003
  • Tele-operation and remote monitoring techniques are essential and important technologies for performing the inspection and repair tasks effectively in nuclear power plants. This paper presents the application of a mobile robot for the remote monitoring and inspection of the Calandria faces, where human access is limited because of the high-level radioactive environments during full power operation. The mobile robot was designed with reconfigurable crawler type of wheels attached on the front and rear side in order to pass through the ditch. The extendable mast, mounted on the mobile robot, can be extended up to 8 m vertically. This robot was also equipped a visible CCD/thermal infrared inspection head module and a stereo camera module for the enhancement of visual inspection.

  • PDF

Review of the regulatory periodic inspection system from the viewpoint of defense-in-depth in nuclear safety

  • Lim, Jihan;Kim, Hyungjin;Park, Younwon
    • Nuclear Engineering and Technology
    • /
    • v.50 no.7
    • /
    • pp.997-1005
    • /
    • 2018
  • The regulatory periodic safety inspection system is one of the most important methods for confirming the safety of nuclear power plants and the defense in depth in nuclear safety is the most important basic means for accident prevention and mitigation. Recently, a new regulatory technology based on risk-informed and safety performance has been developed and used in advanced countries. However, since the domestic periodic inspection system is being used in the same way over 30 years, it is necessary to know how the inspection contributes to the safety confirmation of the nuclear power plants. In this study, the domestic periodic inspection system currently in use was analyzed from the perspective of defense in depth in nuclear safety. In addition, the analysis results were compared to the U.S. NRC's safety inspection system to obtain consistency and lessons in this study. As a result of analysis, the NRC's safety inspections were distributed almost evenly at the all levels of defense in depth, while in the case of domestic inspection, they were heavily focused on the level 1 of defense in depth. Therefore, it appeared urgent to improve the inspection system to strengthen the other levels of defense in depth in nuclear safety.

Wolsong 3&4 Steam Generator Tube Inspection (월성 3,4호기 증기발생기 전열관 검사)

  • Jang, Kyoung-Sik;Kwon, Dong-Ki;Choi, Jin-Hyuk;Son, Tai-Bong
    • Proceedings of the KSME Conference
    • /
    • 2001.11b
    • /
    • pp.859-866
    • /
    • 2001
  • During the Pre-service Inspection for Wolsong Unit 3&4 in 1997/1998 respectively, 17 Distorted Roll Transition indications(over expanded beyond tubesheet secondary face) were identified at the Unit 4 (S/G B, D). Six(6) tubes out of these tubes were plugged in 1998. However the first Periodic Inspection identified additional 110 indications in 1999 and 2000. The additionally identified 110 indication call, not reported at the Pre-service Inspection, are; 2 Not-Finally-Expanded-Tubes and 108 Distorted Roll Transition tubes. Design limit of each Steam Generator tube Plugging is 6.4%. Plugging was performed by the Steam Generator manufacturer under the warranty. When Distorted Roll Transition indications were first identified on the Unit 4 in 1998 the degree of Over-expansion was measured using an inner dial-gage to make the disposition of Nonconformance report. 2 Not-Finally-Expanded-Tubes were plugged and 10 tubes out of 108 Distorted Roll Transition Tubes were also plugged as a preventive measure.

  • PDF

Effect of Inspection on Failure Probability of Pipes in Nuclear Power Plants (원전 배관의 파손확률에 대한 검사의 영향)

  • Park, Jai-Hak;Choi, Young-Hwan
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.36 no.10
    • /
    • pp.1249-1254
    • /
    • 2012
  • Pipe inspections conducted in nuclear power plants play an important role in ensuring the structural integrity of pipes. Because considerable manpower and expense is required for pipe inspections, it is very important to determine the optimum inspection period and the level of inspection. In this study, the effects of the period and the inspection quality on the failure probability of pipes are investigated using the P-PIE program, which has been developed to calculate the failure probability of pipes. The pipe data of an internal nuclear power plant is used in the study, and fatigue and stress corrosion crack growth are considered in the analysis.

The Development of the Data Error Inspection Algorithm for the Remote Sensing by Wireless Communication (원격계측을 위한 무선 통신 에러 검사 알고리즘 개발)

  • 김희식;김영일;설대연;남철
    • Proceedings of the Korean Society of Precision Engineering Conference
    • /
    • 2004.10a
    • /
    • pp.993-997
    • /
    • 2004
  • A data error inspection algorithm for wireless digital data communication was developed. Original data converted By wireless digital data error inspection algorithm. Wireless digital data is high possibility to get distortion and lose by noise and barrier on wireless. If the data check damaged and lost at receiver, can't make it clear and can't judge whether this data is right or not. Therefore, by wireless transmission data need the data error inspection algorithm in order to decrease the data distortion and lose and to monitoring the transmission data as real time. This study consists of RF station for wireless transmission, Water Level Meter station for water level measurement and Error inspection algorithm for error check of transmission data. This study is also that investigation and search for error inspection algorithm in order to wireless digital data transmission in condition of the least data's damage and lose. Designed transmitter and receiver with one - chip micro process to protect to swell the volume of circuit. Had designed RF transmitter - receiver station simply by means of ATMEL one - chip micro processing the systems. Used 10mW of the best RF power and 448MHz-449MHz on frequency band which is open to public touse free within the limited power.

  • PDF

Technical Feasibility Study on the Biomimetic Drone for Inspection of Electric Power Lines (전력선로 점검용 생체모방형 드론에 관한 기술적 실현가능성 연구)

  • Park, Joon-Young;Lee, Jae-Kyung;Kim, Seok-Tae
    • KEPCO Journal on Electric Power and Energy
    • /
    • v.2 no.4
    • /
    • pp.543-548
    • /
    • 2016
  • Live-line maintenance for electric power lines is very dangerous because of their ultra-high voltage environments and the risks of falling from heights. Recently, drone technology has been spotlighted due to its maneuverability and stable controllability, and has been being applied to maintenance works in the electric power industry. This paper presents a new type of drone that can be transformable by introducing biomimetics to its mechanism and can run on an overhead ground wire as well as it can fly. Its technical feasibility was confirmed through experiments.

Development of a Web-based Fatigue Life Evaluation System for Primary Components in a Nuclear Power Plant (원자력발전소 1 차 계통 주요기기에 대한 웹기반 피로수명평가 시스템 개발)

  • Seo, Hyong-Won;Lee, Sang-Min;Choi, Jae-Boong;Kim, Young-Jin;Choi, Sung-Nam;Jang, Ki-Sang;Hong, Sung-Yull
    • Proceedings of the KSME Conference
    • /
    • 2003.04a
    • /
    • pp.279-284
    • /
    • 2003
  • A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including regular in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage the integrity issues on a nuclear power plant. In this paper, a web-based fatigue life evaluation system for primary components in nuclear power plant is proposed. This system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant.

  • PDF