• 한국정보통신학회:학술대회논문집
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• 한국정보통신학회 2014년도 춘계학술대회
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• pp.496-499
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• 2014

30MeV Cyclotron의 양성자가 Xe-124 기체 표적 시스템에 조사될 때 가능한 핵반응을 적용하여 Xe Gas를 GPM으로부터 Target으로 까지 전송하는 시스템을 설계하고 제작하였다. 시스템 설계는 크게 4파트로 나누어 설계하였다. 각각의 하드웨어 부분은 솔리드웍스를 이용하여 설계하였다. Target은 헬륨으로 Havor Foil을 쿨링시키게 설계했고 물은 타겟에 들어간 Xe Gas를 조사 시 높아지는 온도를 식혀주는 역할을 하게 제작하였고 온도센서와 압력센서를 장착하여 눈으로 확인할 수 있게 제작하였다. GPM(Gas Process Manifold)은 Xe Gas를 운반하도록 준비하는 부분이며 Xe Gas를 담고있는 부분과 불순물을 제거하는 부분이 있다. HCS(Helium Circulation System)은 헬륨을 이용하여 각파트를 클리닝 하고 냉각시켜 준다. 이러한 각 부분들을 PLC로 제어하게 하여 유지보수시의 편리성을 추구하였고 PC Vue를 사용하여 SIEMENS PLC를 더욱더 안전하게 인터페이스하게 하였다.

• 한국정보통신학회논문지
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• 제18권6호
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• pp.1462-1468
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• 2014

30MeV 사이클로트론의 양성자가 Xe-124 기체 표적 시스템에 조사될 때 일어나는 핵반응을 적용하여 Xe 가스를 GPM으로부터 타겟으로 전송하는 시스템을 설계하였다. 시스템 설계는 크게 4파트로 구성되며 각각의 하드웨어 부분은 솔리드웍스 3-D 캐드를 이용하여 설계하였다. 타겟 시스템 중 헬륨으로 Havor foil을 냉각시키게 설계했고, 타겟 내 Xe 가스가 양성자로 조사 시 상승하는 타겟 온도를 냉각수로 냉각시켜주도록 설계하였다. 또한, 온도센서와 압력센서를 장착하여 타겟 내의 온도와 압력을 확인할 수 있도록 구성 하였다. GPM은 Xe 가스를 타겟으로 운반, 준비하는 부분이며 Xe 가스를 저장하는 부분과 불순물을 제거하는 부분으로 구성되어 있다. HCS는 헬륨을 이용하여 각 파트를 세척하고 냉각시켜 주는 부분이며, 각각의 장치들은 PLC로 제어하여 유지보수시의 편리성을 추구하였고 PC Vue 모니터링 프로그램을 사용하여 SIEMENS PLC와 인터페이스 하여 시스템을 보다 안전하고 편리하게 감시하도록 구성하였다.

• Nuclear Engineering and Technology
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• 제48권5호
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• pp.1273-1279
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• 2016

Production of iodine-131 by neutron activation of tellurium in tellurium dioxide ($TeO_2$) material requires a target that meets the safety requirements. In a radiopharmaceutical production unit, a new lid for a can was designed, which permits tight sealing of the target by using tungsten inert gaswelding. The leakage rate of all prepared targets was assessed using a helium mass spectrometer. The accepted leakage rate is ${\leq}10^{-4}mbr.L/s$, according to the approved safety report related to iodine-131 production in the TRIGA Mark II research reactor (TRIGA: Training, Research, Isotopes, General Atomics). To confirm the resistance of the new design to the irradiation conditions in the TRIGA Mark II research reactor's central thimble, a study of heat effect on the sealed targets for 7 hours in an oven was conducted and the leakage rates were evaluated. The results show that the tightness of the targets is ensured up to $600^{\circ}C$ with the appearance of deformations on lids beyond $450^{\circ}C$. The study of heat transfer through the target was conducted by adopting a one-dimensional approximation, under consideration of the three transfer modes-convection, conduction, and radiation. The quantities of heat generated by gamma and neutron heating were calculated by a validated computational model for the neutronic simulation of the TRIGA Mark II research reactor using the Monte Carlo N-Particle transport code. Using the heat transfer equations according to the three modes of heat transfer, the thermal study of I-131 production by irradiation of the target in the central thimble showed that the temperatures of materials do not exceed the corresponding melting points. To validate this new design, several targets have been irradiated in the central thimble according to a preplanned irradiation program, going from4 hours of irradiation at a power level of 0.5MWup to 35 hours (7 h/d for 5 days a week) at 1.5MW. The results showthat the irradiated targets are tight because no iodine-131 was released in the atmosphere of the reactor building and in the reactor cooling water of the primary circuit.

• Nuclear Engineering and Technology
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• 제39권1호
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• pp.1-8
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• 2007

Hydrogen and electricity are expected to dominate the world energy system in the long term. The world currently consumes about 50 million metric tons of hydrogen per year, with the bulk of it being consumed by the chemical and refining industries. The demand for hydrogen is expected to increase, especially if the U.S. and other countries shift their energy usage towards a hydrogen economy, with hydrogen consumed as an energy commodity by the transportation, residential and commercial sectors. However, there is strong motivation to not use fossil fuels in the future as a feedstock for hydrogen production, because the greenhouse gas carbon dioxide is a byproduct and fossil fuel prices are expected to increase significantly. An advanced reactor technology receiving considerable international interest for both electricity and hydrogen production, is the modular helium reactor (MHR), which is a passively safe concept that has evolved from earlier high-temperature gas-cooled reactor (HTGR) designs. For hydrogen production, this concept is referred to as the H2-MHR. Two different hydrogen production technologies are being investigated for the H2-MHR; an advanced sulfur-iodine (SI) thermochemical water splitting process and high-temperature electrolysis (HTE). This paper describes pre-conceptual design descriptions and economic evaluations of full-scale, nth-of-a-kind SI-Based and HTE-Based H2-MHR plants. Hydrogen production costs for both types of plants are estimated to be approximately $2 per kilogram.

• 대한기계학회논문집A
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• 제34권9호
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• pp.1241-1248
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• 2010

초고온가스로에서 생성된 $950^{\circ}C$ 정도의 초고온 열을 이용하여 수소를 경제적이며 또한 대량으로 생산하기 위한 시스템이 원자력수소생산시스템이며, 공정열교환기는 초고온 열과 황-요오드 공정을 통해 수소를 생산하는 원자력수소생산시스템에서의 핵심 기기이다. 한국원자력연구원에서는 초고온가스로에 사용될 기기에 대한 성능시험을 위해 최대 작동 설계온도 $1000^{\circ}C$인 헬륨가스루프를 구축하고 있으며 공정열교환기를 설계하였다. 본 연구에서는 구축중인 헬륨가스루프에서 성능시험을 수행할 예정으로 설계된 공정열교환기에 대한 고온 구조건전성을 미리 평가하기 위한 작업의 일환으로 고온구조해석 모델링, 열해석 및 열팽창 해석을 수행한 결과를 정리한 것이다. 해석결과를 이용하여 설계된 공정열교환기의 구조건전성을 유지하기 위한 1 차 및 2 차 열매체의 유입/유출 파이프라인에서의 적절한 구속조건을 결정하였으며 이를 향후 제작될 공정열교환기 시제품의 성능시험 장치 설계에 반영할 것이다.

• 한국수소및신에너지학회논문집
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• 제34권3호
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• pp.267-273
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• 2023

As the impacts of global climate change become increasingly apparent, the reduction of carbon emissions has emerged as a critical subject of discussion. Nuclear power has garnered attention as a potential carbon-free energy source; however, the rapidity of load following in nuclear power generation poses challenges in comparison to fossil-fueled methods. Consequently, power-to-gas systems, which integrate nuclear power and hydrogen, have attracted growing interest. This study presents a preliminary design of a very high temperature reactor (VHTR) integrated blue hydrogen production process utilizing DWSIM, an open-source process simulator. The blue hydrogen production process is estimated to supply the necessary calorific value for carbon capture through tail gas combustion heat. Moreover, a thermodynamic assessment of the main recuperator is performed as a function of the helium flow rate from the VHTR system to the blue hydrogen production system.

• 대한기계학회논문집A
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• 제28권4호
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• pp.435-442
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• 2004

This paper presents a hermetic MEMS on-chip package bonded by a closed-loop AuSn solder-line. We design three different package specimens, including a substrate heated specimen without interconnection-line (SHX), a substrate heated specimen with interconnection-line (SHI) and a locally heated specimen with interconnection-line (LHI). Pressurized helium leak test has been carried out for hermetic seal evaluation in addition to the critical pressure test for bonding strength measurement. Substrate heating method (SHX, SHI) requires the bonding time of 40min. at 400min, while local heating method (LHI) requires 4 min. at the heating power of 6.76W. In the hermetic seal test. SHX, SHI and LHI show the leak rates of 5.4$\pm$6.7${\times}$$^{-10}$ mbar-l/s, 13.5$\pm$9.8${\times}$$^{-10}$ mbar-l/s and 18.5$\pm$9.9${\times}$$^{-10}$ mbar-l/s, respectively, for an identical package chamber volume of 6.89$\pm$0.2${\times}$$^{-10}$. In the critical pressure test, no fracture is found in the bonded specimens up to the applied pressure of 1$\pm$0.1MPa, resulting in the minimum bonding strength of 3.53$\pm$0.07MPa. We find that the present on-chip packaging using a closed AuSn solder-line shows strong potential for hermetic MEMS packaging with interconnection-line due to the hermetic seal performance and the shorter bonding time for mass production.

• 한국수소및신에너지학회논문집
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• 제35권4호
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• pp.353-362
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• 2024

In this study, several studies were conducted on the construction of gas conversion process system for a pilot plant using a small-scale hydrogen liquefaction system. The pilot plant considered in this study includes a liquefier, a storage tank, an evaporator, a gas booster, and a gas storage tank. First, the suspected leak area of the container was checked using the sprayed method of helium gas. The small-scale hydrogen liquefaction system was designed based on the analysis results of the pre-cooling system and the liquefaction system. Additionally, the program was developed to maintain pressure within vessel for an automatic production of liquid hydrogen. The evaporator for liquid hydrogen was manufactured based on the designed analysis data, and the pollution of gas in the vessel was analyzed through a gas recovery line system.

• 한국초전도ㆍ저온공학회논문지
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• 제24권3호
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• pp.24-29
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• 2022

One of the recent proposals with nuclear magnetic resonance (NMR) is a multi-bore NMR which consists of array of magnets which could present possibilities to quickly cope with pandemic virus by multiple inspection of virus samples. Low temperature superconductor (LTS) can be a candidate for mass production of the magnet due to its low price in fabrication as well as operation by applying the helium zero boil-off technology. However, training feature of LTS magnet still hinders the low cost operation due to multiple boil-offs during premature quenches. Thus in this paper, LTS magnet with low mechanical stress is designed targeting the "training-free" LTS magnet for mass production of magnet array for multi-bore NMR. A thorough process of an LTS magnet design is conducted, including the analyses as the followings: electromagnetics, mechanical stress, cryogenics, stability, and protection. The magnet specification was set to 4.7 T in a winding bore of 85 mm, corresponding to the MR frequency of 200 MHz. The stress level is tolerable with respect to the wire yield strength and epoxy crack where mechanical disturbance is less than the minimum quench energy.

• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2564-2569
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• 2021

The neutronic analysis of Helium Cooled Ceramic Reflector (HCCR) breeding blankets has been performed using the 3D Monte Carlo code MCNPX and ENDF nuclear data library. This study aims to reduce ⁶Li percentage in the breeder zones as much as possible ensuring tritium self-sufficiency. This work is devoted to investigating the effect of ⁶Li percentage on the HCCR breeding blanket's neutronic parameters, such as neutron flux and spectrum, Tritium Breeding Ratio (TBR), nuclear power density, and energy multiplication factor. In the ceramic breeders at the saturated thickness, increasing the enrichment of ⁶Li reduces its share in the tritium production. Therefore, ceramic breeders typically use lower enriched Li from 30% to 60%. The investigation of neutronic analysis in the suggested geometry shows that using 60% ⁶Li in Li₂TiO₃ can yield acceptable TBR and energy deposition results, which would be economically feasible.