• Proceedings of the Korean Institute of Building Construction Conference
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• 2018.05a
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• pp.60-61
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• 2018

Finishing materials are very important to restrain fire spread from a compartment to another in a fire situation. Therefore, the evaluation of combustible properties for the combustible material is essential to apply finishing materials into a generic buillding or s special occupancy structure. In this study, the testing methods for evaluation of combustible performance of finishing materials of domestic were surveyed in order to prepare the guideline of application of finishing materials in nulear power plant.

• Journal of Applied Reliability
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• v.14 no.4
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• pp.248-255
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• 2014

Nuclear power plants may use commercial grade items if they can pass special tests or inspections, which is called Commercial Grade Item Dedication (CGID). Digital items, however, should follow EPRI TR-106439 to be applied to nuclear power plants. This paper explains the scheme and requirements of the EPRI TR-106439 and introduces some guidelines. Firstly, in order to clarify requirements of the EPRI TR-106439, code interpretation is performed. And through case study of digital indicator, limitations of EPRI TR-106439 are mentioned, and improvement direction is proposed.

• Journal of the Korean Society for Nondestructive Testing
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• v.26 no.6
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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.

• Journal of the Korean Society for Nondestructive Testing
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• v.9 no.2
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• pp.42-49
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• 1989

It has not been performed to inspect the underclad cracking in Korea nuclear plant since there is no Code Requirements for inspection. However, underclad cracks in nuclear pressure vessels were reported firstly in 1970. The objection of this study is to be established the ultrasonic inspection techniques for underclad cracking. The ultrasonic inspection of bimetalic stainless steel weld is very difficult by high attenuation and multiple scattering at weld surface and weld/base metal interface. The various inspection methods using $70^{\circ}$ refracted longitudinal wave, 50/70 tandem transducer, $45^{\circ}\;and\;60^{\circ}$ single shear wave are compared. Experiments on limited specimens applied same condition to nuclear pressure vessels shows that $70^{\circ}$ refracted longitudinal wave method is the best one for the detection of underclad cracks. 50/70 tandem transducer using SPOT(Satellite Pulse Observation Technique) is more effective for underclad crack sizing than other sizing methods.

• Transactions of the Korean hydrogen and new energy society
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• v.33 no.6
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• pp.761-768
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• 2022

In the hope of realizing carbon neutrality, Korea has established the goal of expanding the supply of hydrogen electric vehicles through a roadmap to revitalize the hydrogen economy. A prerequisite for successful supply expansion is securing the safety of hydrogen electric vehicles. Certain parts, such as the hydrogen transport pipe and tank, in hydrogen electric vehicles are exposed to high-pressure hydrogen gas over long periods of time, so the hydrogen enters the grain boundary of material, resulting in a degradation of the parts referred to as hydrogen embrittlement. In addition, since the safety of parts utilizing hydrogen varies depending on the type of material used and its environmental characteristics, the necessity for the enactment of a hydrogen embrittlement regulation has emerged and is still being discussed as a Global Technical Regulation (GTR). In this paper, we analyze a hydrogen compatibility material evaluation method discussed in GTR and present a direction for the development of Korean-type hydrogen compatibility material evaluation methods.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.430.1-430
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.473.2-473
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.182.1-182
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.237.1-237
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.265.2-265
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• 2001