• 제어로봇시스템학회:학술대회논문집
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• 2000.10a
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• pp.379-379
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• 2000

The robot systems used in nuclear power plants need to be both reliable and safe. As a part of the "Validation of nuclear safety-grade equipment" project, we established reliability analysis program and performed a number of analysis using conventional reliability analysis techniques. This paper describes the procedures, techniques, and results of the analysis utilized in our project. In addition, the paper includes current status of reliability analysis techniques and the summary of foreign case studiesse studies

• Journal of Fisheries and Marine Sciences Education
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• v.27 no.5
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• pp.1265-1272
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• 2015

This study aims at comparison and analyzing of marine officer license system for fishing vessels between South Korea and New Zealand. It is urgently required to establish Republic of Korea-New Zealand mutual certification system for marine officers who are on board ships within applicable area given that New Zealand will force foreign fishing vessels within New Zealand area to reflag from 2016 in accordance with the amendment of Fisheries Act. Secondly, to compare and analyze systems between two countries will contribute to the preparatory work related to ratification STCW-F convention as New Zealand already have completed law amendment to adapt the convention. Maritime law of New Zealand, Seafarers Act and Ship Personnel Act of Republic of Korea were compared and analyzed as references. The result showed that an improvement to corresponding level to the international convention and development of safety training by vessel type, and job descriptions according to the license class are needed to Republic of Korea system. Furthermore, it is suggested to prepare specialized training for deckhands as required in STCW-F convention and standard fishing vessel officer training record for designated institute of education. Therefore institutional complementarity and framework is required as it is expected that the nations of fishing in piscary demand to reflag Korean deep-sea fishing vessels or to ratify the STCW-F convention.

• Journal of the Korean Institute of Navigation
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• v.23 no.4
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• pp.43-61
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• 1999

To ensure ship's safety and preserve the marine environment from ship, IMO(International Maritime Organization) has been making much efforts. Nevertheless there are still many possibilities threatening ship's safety and the marine environment. Many vessels navigate at sea in lack of standard required by the International Convention relevant to ship's safety and the protection of marine environment. Even though the administration is responsible for perfect and continuous control for safety of ship, it cannot has jurisdiction over ships hoist its flag reasonably at all times. So the Port State has strengthened the Port State Control(PSC) activity as one step of eliminating sub-standard vessels. In the light of the fact that mentioned above, this study deals with PSC activity in Korea and port of Pusan. Total 582 ships, inspected in port of Pusan from 1st January 1998 to 30th September 1999, were analyzed in various aspect and extracted results as follows : \circled1 The inspection rate in Korea was much lower than the other states taking part in Tokyo MOU, \circled2 For flag state, the ships belong to flag of convenience(FOC) had much more deficiencies than non-convenience flag ships, \circled3 For ship type, 39 number of general dry cargo ship were detained at Pusan with serious deficiencies, \circled4 For deficiency item, the items such as life saving appliances, safety in general, navigation, load lines and fire-fighting appliances were occupied over 71.7% of total number of deficiencies, \circled5 In Asia-Pacific region, Korea was one of flags with detention percentages exceeding 3-year(1996~1998) rolling average detention percentage. Average detention rate of Korean vessels was 6.73% which was over 0.24% of average detention rate(6.49%) in Asia-Pacific region. These results may reflect to improve the performance of PSC inspection for foreign vessels and are useful for preparing PSC inspection for ocean-going ships registered in Korea.

• Proceedings of the Korean Institute of Navigation and Port Research Conference
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• 2017.11a
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• pp.254-255
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• 2017

As the number of ships and goods shipped by marine transportation increases, almost all shipping companies adopted foreign crews in order to overcome lack of seafarers and be competitive for manning cost. Thus, these days it is inevitable to work with foreign crews aboard ships, but there occur many marine accidents due to language barriers and communication problems under multicultural and multilingual shipboard environments. In order to resolve troubles resulting from different languages, reduce miscommunication risks, and make working on ships safe and efficient, this study recognized the current status of ships with mixed crews, analyzed marine accidents caused by communication problems not only in Korea but also in other countries using analytical methodologies. Additionally, existing hazards affecting miscommunication were identified and risk of miscommunication was quantitatively evaluated while offering suggestions and future forecasts. Consequently, in this study we suggested that fundamental dialogues are to be necessarily educated on the ships with foreign crews so as to reduce the language barrier and risk of miscommunication. Furthermore, a standard maritime Korean language program and manual targeting Korean coastal vessels would be developed in the next step.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.7 no.3
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• pp.61-66
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• 2011

The integrity of the SG(Steam Generator) tubes has been challenged by numerous factors such as flaws, operation, atmosphere, inherently degraded materials, loose parts and even human errors. Of the factors, loose parts(or foreign materials) on the secondary side of the tubes can bring about volumetric defects and even leakage from the primary to the secondary side in a short period of time. More serious concerns about the loose parts are their unknown influx path and rapid growth rate of the defects affected by the loose parts. Therefore it is imperative to detect and characterize the foreign materials and the defects. As a part of the measures for loose part detection, TTS(Top of Tubesheet) MRPC(Motorized Rotating Pancake Coils) ECT has been carried out especially to the restricted high probability area of the loose part. However, in the presence of loose parts in the other areas, wide range loose part detection techniques are required. In this study, loose part standard tube was presented as a way to accurately detect and characterize loose part signals. And the SG tube ECT bobbin coil and MRPC ISI(In-service Inspection) data of domestic OPR-1000 and Westinghouse Model F(W_F) were reviewed and consequently, comprehensive loose part detection technique is derived especially by applying bobbin coil signals

• Journal of Environmental Science International
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• v.20 no.5
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• pp.655-665
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• 2011

Contamination of butyltin compounds (BTs), namely tributyltin (TBT), dibutyltin (DBT) and monobutyltin (MBT), was evaluated in sediments collected inside Jeju Harbor in 2001. The concentrations of BTs in surface sediments were comparable to those in other sites of domestic and foreign countries. The high correlations between BTs in surface ($r^2$ = 0.83~0.91) and core ($r^2$ = 0.70~0.79) sediments and the significant correlations between BTs concentrations and the number of incoming and outgoing vessels indicated that DBT and MBT were mainly degraded from TBT based on antifouling paints of vessels etc. and other sources, such as DBT and MBT, could be ignored. The butyltin degradation indices ([DBT] + [MBT]/[TBT]) in surface sediments were in the range of 2.2~3.6 (mean 2.7), indicating that the parent compound, TBT, was inflowed into the surface sediments a long ago, degraded and deposited. The sedimentation age of BTs contaminated core sediments could not estimated because the content of $^{210}Pb$ activity was nearly all the same and so the sedimentation rate could not obtained.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.9 no.1
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• pp.40-47
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• 2013

The capacity factor of nuclear power plant in Korea is the highest level in the world. However, the integrity assessment of nuclear power plant is depended on foreign country. Especially, most eddy current testing systems for inspecting steam generators in nuclear power plant are currently imported from USA, Canada, and so on. Therefore, the eddy current testing system can react more active and adaptive from economic and managerial standpoint for actual nuclear power plants in Korea is required. In this paper, an eddy current testing system for inspecting steam generators in nuclear power plants is introduced. Frequency generator, analog circuit, analog digital converter circuit, and digital control circuit are composed in eddy current testing system. A benchmarking of acquisition system and acquisition software, eddynet 11i made by Zetec, and modifications are carried out based on the test environment of Korea nuclear power plants. Finally, all eddy current apparatus are integrated to inspect steam generator tubes in nuclear power plants.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.16 no.1
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• pp.84-91
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• 2020

The APR1400 reactor stud holes can be stuck due to high temperatures, high pressure, prolonged engagement, and load changes according to pressure changes in the reactor. Threaded surfaces of a stud hole should be cleaned for the sealing of pressure in reactor vessel by removing any foreign materials which may exist in the stud holes. Human workers can access to the stud hole for the cleaning of stud holes manually, but the radiation exposure of human workers is increased. Robot is an effective way to work in hazardous area. So we introduced robot for the cleaning of stud holes. Localization of mobile robots is generally based on odometry, but with increased mileage, position errors can be accumulated. In order to eliminate cumulative error and to ensure stability of its driving, laser sensors and new control algorithm were utilized. The distance between the robot and the wall was measured by laser sensors, and the control algorithm was implemented so as to travel the desired trajectory by using the measured values from sensors. The performance of driving and hole sensing were verified through field application, and mobile robot was confirmed to be applicable to the APR 1400 NPP.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.7 no.4
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• pp.19-25
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• 2011

Steam Generator(SG) tube is an important component of Nuclear Power Plant(NPP), which is the pressure boundary between the primary and secondary systems. The integrity of SG tube has been confirmed by the eddy current test every outage. The eddy current technique adopting bobbin probe is currently the primary technique for the steam generator tubing integrity assesment. The bobbin probe is one of the essential components which consist of the whole ECT examination system and provides us a decisive data for the evaluation of tube integrity. Until now, all of the ECT bobbin probes in Korea which is necessary to carry out inspection are imported from overseas. However, KHNP has recently developed the bobbin probe design technology and transferred it to domestic manufacturers to fabricate the probes. This study has been conducted to establish technical requirements applicable to the steam generator tube inspection using the bobbin probes fabricated by the domestic manufactures. The results have been compared with the results obtained by using foreign probe to identify the availability to the steam generator tube inspection. As a result, it is confirmed that the domestic bobbin probe is generally applicable to SG tube inspection in the NPPs.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.7 no.3
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• pp.8-14
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• 2011

The clogging of the flow area at the tube support plates(TSPs), especially at the upper TSPs results in the water level oscillation of a steam generator during normal operation. A reduction of the TSP flow area causes to increase in pressure drop within the two-phase flow zone, which destabilizes the boiling flow through the tube bundle. This phenomenon was occasionally observed at a few domestic and foreign nuclear power plants. One of the methods for defining the flow area clogging is visual inspection, which is the most effective inspection method. The results of the visual inspection for TSPs' flow area are clogging images on TSPs' quartrefoil lobes. These images are complexly distorted due to lens aberration and external factors like the distance to a subject and angle etc. In this work, we developed the analysis algorithm for clogging image of the TSP flow area of steam generators. For this purpose, we designed an image verification device applicable to the camera employed in the field for visual inspection and then, we demonstrated the validity of image analysis algorithm by using this device and commercial autoCAD program.