• Journal of Korean Society of Industrial and Systems Engineering
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• v.33 no.4
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• pp.114-121
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• 2010

Traditionally Nuclear Research and Development (R&D) result has been big influence on other industries and societies and it requires large scale investments and study period. So it is essential to apply Quality Assurance (QA) for systematic R&D management. This paper investigates QA System for U.S. Nuclear R&D and reviews QA elements. Based on this investigation, we applied QA requirements to Nuclear Hydrogen R&D project, and the scope of application be enlarged as R&D stage in progress. We also present QA system improvement way through consideration for Nuclear Hydrogen Project's QA application. As the need for QA in R&D is expected to increase in the future, it is necessary to prepare guidelines for R&D QA.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.8 no.1
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• pp.1-7
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• 2012

A PHE (Process Heat Exchanger) is a key component required to transfer heat energy of $950^{\circ}C$ generated in a VHTR (Very High Temperature Reactor) to the chemical reaction that yields a large quantity of hydrogen. A small-scale PHE prototype made of Hastelloy-X is being tested in a small-scale gas loop at Korea Atomic Energy Research Institute. In order to properly evaluate the high-temperature structural integrity of the small-scale PHE prototype, it is very important to impose a proper constraint condition on its structural analysis model. For this effort, we tried to impose several constraint conditions on the structural analysis model and consequently fixed a proper and effective displacement constraints.

• Proceedings of the Korean Society of Propulsion Engineers Conference
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• 2008.05a
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• pp.9-13
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• 2008

The moving load such as a shock wave in a pipe propagates with a specific velocity. This internal load speed determines the level of flexural wave excitation and the possibility of resonant response leading to a large deformation. In this paper, we present particular solutions of displacements and the resonance conditions when the moving load is propagating in a pipe. These analytical results are compared to numerical simulations obtained using a hydrocode. We expect to identify potential explosion hazards in the general power industries.

• Proceedings of the KSME Conference
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• 2008.11a
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• pp.717-724
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• 2008

Very High Temperature Gas Cooled Reactor (VHTR) has been selected as a high energy heat source for nuclear hydrogen generation, which can produce hydrogen from water or natural gas. A primary hot gas duct (HGD) as a coaxial double-tube type cross vessel is a key component connecting the reactor pressure vessel and the intermediate heat exchanger for the VHTR. In this study, structural sizing methodology for the primary HGD with a coaxial double-tube of the VHTR that produces heat at temperatures in the order of $950^{\circ}C$ was suggested and a structural pre-sizing of it was carried out as an example.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.7 no.3
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• pp.48-53
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• 2011

A PHE (Process Heat Exchanger) is a key component required to transfer heat energy of $950^{\circ}C$ generated in a VHTR (Very High Temperature Reactor) to the chemical reaction that yields a large quantity of hydrogen. A small-scale PHE prototype made of Hastelloy-X is being tested in a small-scale gas loop at Korea Atomic Energy Research Institute. In this study, as a part of the evaluation on the high-temperature structural integrity of the small-scale PHE prototype, we carried out macroscopic high-temperature structural analysis of the small-scale PHE prototype under the gas loop test conditions considering the pipeline stiffness.

• Nuclear Engineering and Technology
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• v.15 no.2
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• pp.149-153
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• 1983

The removal of zinc (II) from aqueous solutions has been studied by the adsorptive bubble separation processes such as solvent sublation and foam fractionation processes using capric acid as collector. The efficiency of the remoal process has been studied by changing the ionic strength and pH and the bubble separation method has been compared with the solvent extraction process using the capric acid dissolved in benzene as extractant.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.9 no.4
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• pp.231-236
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• 2011

When the Fukushima nuclear power plant accident occurred in March of 2011, a hydrogen explosion in the reactor building at the 4th unit of Fukushima plants led to a big surprise because the full core of the unit 4 reactor had been moved and stored underwater at the spent nuclear fuel storage pool for periodic maintenance. It was because the possible criticality in the fuel storage pool by coolant loss may yield more severe situation than the similar accident happened inside the reactor vessel. Fortunately, it was assured to be evitable to an anxious situation by a look of water filled in the storage pool later. In the paper, the safety state of the spent fuel storage pool and rack structures of the domestic nuclear plants would be roughly reviewed and compared with the Fukushima plant case by engineering viewpoint of potential severe accidents.

• Proceedings of the Korean Vacuum Society Conference
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• 2012.02a
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• pp.173-173
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• 2012

사이클로트론은 암진단에 사용되는 방사성동위원소를 생산하기 위한 중요한 입자 가속장치이다. 현재 핵의학 의료진단에 필요한 방사성동위원소를 제공하기 위해 세계적으로 사이클로트론의 활용도가 점점 증가하고 있다. 한국원자력의학원에 설치된 MC50 (양성자 최대 가속에너지 50 MeV, 60 uA)과 C30 (양성자 최대 에너지 30 MeV, 250 uA) 사이클로트론은 생명의학, 반도체 검출기, 핵자료 데이터, 방사성동위원소 개발 등 다양한 분야의 연구를 지원하고 있다. MC50 사이클로트론은 수소 입자를 포함하여 중양자, 알파 입자를 가속할 수 있으며 중성자 빔을 인출 할 수 있다. 수소 음이온 또는 양이온을 가속 할 수 있으며 표적에는 고에너지의 양이온이 조사되며, 핵반응을 통해 방사성동위원소가 생성된다. 양성자 빔을 이용하여 암세포를 사멸 시키는 치료법, 돌연변이로 새로운 종의 개발 등 다양한 응용성이 있다. 하전입자를 가속하는 사이클로트론의 주요 구성요소는 (1) 진공시스템, (2) 전자석 시스템, (3) 고주파 시스템, (4) 이온원 (5) 빔 인출장치 (6) 빔전환 장치 (수직에서 수평 방향으로 전환), (7) 빔 집속 및 진단 장치 등 이다. 본 발표에서는 85년부터 운영한 MC50 사이클로트론과 02년부터 가동된 사이클로트론의 운영 현황 및 다양한 응용분야와 향후 RI 빔 인출을 위한 계획을 소개하고자 한다.

• Journal of Radiation Protection and Research
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• v.35 no.1
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• pp.12-20
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• 2010

In a primary system at nuclear power plants (NPPs), various radionuclides including fission products and corrosion products are generated due to the complex water conditions. Particularly, $^3H,\;^{14}C,\;^{58}Co,\;^{60}Co,\;^{137}Cs,\;and^{131}I$ are important radionuclides in respect of dose assessment for radiation workers and management of radioactive effluents. In this paper, the dominant contributors of radiation exposure for radiation workers and the member of public adjacent to NPPs were reviewed and the process of dose assessment attributable to those contributors were introduced. Furthermore, the analysis for some examples of radiation exposure to radiation workers and the public during the NPP operation was carried out. This analysis included the notable precedents of internal radiation exposure and contamination of demineralized water occurred in Korean NPPs. Particularly, the potential issue about the dose assessment of tritium and carbon-14 was also reviewed in this paper.

• Tunnel and Underground Space
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• v.31 no.5
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• pp.333-359
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• 2021

Gases such as hydrogen and radon can be generated around the canister in high-level radioactive waste disposal systems due to several reasons including the corrosion of metal materials. When the gas generation rate exceeds the gas diffusion rate in the low-permeability bentonite buffer, the gas phase will form and accumulate in the engineered barrier system. If the gas pressure exceeds the gas entry pressure, gas can migrate into the bentonite buffer, resulting in pathway dilation flow and advective flow. Because a sudden occurrence of dilation flow can cause radionuclide leakage out of the engineered barrier of the radioactive waste disposal system, it is necessary to understand the gas migration behavior in the bentonite buffer to quantitatively evaluate the long-term safety of the engineered barrier. Experimental research investigating the characteristics of gas migration in saturated bentonite and research developing numerical models capable of simulating such behaviors are being actively conducted worldwide. In this technical note, previous gas injection experiments and the numerical models proposed to verify such behaviors are introduced, and the future challenges necessary for the investigation of gas migration are summarized.