• Proceedings of the Korean Nuclear Society Conference
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• 1999.05a
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• pp.463-463
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• 1999

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.194.2-194
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• 2002

• Proceedings of the Korean Nuclear Society Conference
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• 2002.10a
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• pp.284-284
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• 2002

• Proceedings of the Korean Nuclear Society Conference
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• 2002.10a
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• pp.154.2-154
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• 2002

• Proceedings of the Korea Society for Energy Engineering kosee Conference
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• 2004.11a
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• pp.317-322
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• 2004

• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.156.1-156
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• 1999

• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.359.2-359
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• 1999

• Journal of the Korean Society for Nondestructive Testing
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• v.26 no.1
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• pp.18-24
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• 2006

Reactor core and internal structures of a liquid metal reactor (LMR) can not be visually examined due to an opaque liquid sodium. The under-sodium viewing technique by using an ultrasonic wave should be applied far the visual inspection of reactor internals. In this study, an ultrasonic waveguide sensor with a strip plate has been developed for an application to the under-sodium viewing technique. The Lamb wave propagation of a waveguide sensor has been analyzed and the zero-order antisymmetric $A_0$ plate wave was selected as the application mode of the sensor. The $A_0$ plate wave can be propagated in the dispersive low frequency range by using a liquid wedge clamped to the waveguide. A new technique is presented which is capable of steering the radiation beam angle of a waveguide sensor without a mechanical movement of the sensor assembly The steering function of the ultrasonic radiation beam can be achieved by a frequency tuning method of the excitation pulse in the dispersive range of the $A_0$ mode. The technique provides an opportunity to overcome the scanning limitation of a waveguide sensor. The beam steering function has been evaluated by an experimental verification. The ultrasonic C-scanning experiments are performed in water and the feasibility of the ultrasonic waveguide sensor has been verified.

• Journal of the Korean Vacuum Society
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• v.13 no.4
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• pp.182-188
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• 2004

Previous studies on the liquid Gallium ion sources used an electro-chemically etched tungsten wire with a coil-type heater. Such a structure requires excessive power consumption in the course of heating the liquid metal. In this work, a new structure is proposed that replaces the coil-type heater. It uses a Gallium reservoir made of six pre-etched 250$\mu\textrm{m}$ tungsten wires that surround the needle electrode. Gallium trading at the reservoir is observed to be much more stable, resulting in an improved beam stability.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.36-41
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• 1997

액체금속로는 고온 하중 효과(피로, 크립, 크립-피로)를 고려한 내열응력설계가 중요하다. 최근에는 액금로 후보재료로서 종래의 스테인레스강에 질소를 첨가하여 고온강도를 계량한 316LN 스테인레스강이 개발되었다. 본 연구에서는 액체금속로 재료의 가장 지배적인 손상 기구로 인식되고 있는 피로-크립 파손에 대한 설계자료를 확보하기 위해 DCPD(Direct Current Potential Drop)법에 의한 고온피로균열 측정 시스템을 개발하고 316L 및 스테인레스강인 316LN 스테인레스강에 대한 고온 피로균열진전시험을 수행하였다. 본 연구에 의해 개발된 피로균열진전속도 측정 시스템에 의하면 25$\mu\textrm{m}$ 이하의 분해능으로 균열길이를 측정할 수 있다. 한편 316L 스테인레스강에 질소를 적당량 첨가하면 상온에서 $600^{\circ}C$사이의 온도에서 피로균열진전에 대한저항성이 증가하는 것을 확인하였다.