• Corrosion Science and Technology
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• 제17권5호
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• pp.218-224
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• 2018

Alloy 617 is a candidate Ni-based superalloy for intermediate heat exchanger (IHX) of a high-temperature gas reactor (VHTR), because of its good creep strength and corrosion resistance at high temperature. Small amount of impurities such as $H_2O$, $H_2$, CO and $CH_4$ are introduced inevitably in helium, as a coolant during operation of a VHTR. Reactions of material and impurities are accelerated with increase of temperature to $950^{\circ}C$ of operating temperature of a VHTR, leading to material corrosion aggravation. In this circumstance, high-temperature corrosion tests were performed at $950^{\circ}C$ in air and impure helium environments, up to 250 hours in this study. Oxidation rate of $950^{\circ}C$ in an air environment was higher than that of impure helium, explained by difference in outer oxide morphology and microstructure as a function of oxygen partial pressure. An equiaxed Cr-rich surface oxide layer was formed in an air environment, and a columnar Cr-rich oxide was formed in an impure helium environment.

• 비파괴검사학회지
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• 제13권3호
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• pp.31-38
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• 1993

포항가속기 저장링 진공챔버는 진공도가 $10^{-10}Torr$로 유지될 수 있도록 설계되었고, 초고진공에 적합하도록 TIG용접을 하여 헬륨에 대한 누설률이 $1{\times}10^{-10}Torr{\cdot}{\ell}/sec$ 이하의 기밀성이 요구되고 있다. 저장링 진공챔버에 적용된 TIG용접방법과 결함에 대해 논하고 누설검사에 사용된 헬륨누설검사기의 원리 및 검사방법에 대해서 보고하고자 한다.

• Nuclear Engineering and Technology
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• 제39권2호
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• pp.95-102
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• 2007

The conceptual design of the MIT modular pebble bed reactor is described. This reactor plant is a 250 Mwth, 120 Mwe indirect cycle plant that is designed to be deployed in the near term using demonstrated helium system components. The primary system is a conventional pebble bed reactor with a dynamic central column with an outlet temperature of 900 C providing helium to an intermediate helium to helium heat exchanger (IHX). The outlet of the IHX is input to a three shaft horizontal Brayton Cycle power conversion system. The design constraint used in sizing the plant is based on a factory modularity principle which allows the plant to be assembled 'Lego' style instead of constructed piece by piece. This principle employs space frames which contain the power conversion system that permits the Lego-like modules to be shipped by truck or train to sites. This paper also describes the research that has been conducted at MIT since 1998 on fuel modeling, silver leakage from coated fuel particles, dynamic simulation, MCNP reactor physics modeling and air ingress analysis.

• 한국초전도저온공학회:학술대회논문집
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• 한국초전도저온공학회 2002년도 학술대회 논문집
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• pp.67-70
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• 2002

The Stirling cryocooler with helium refrigerant has been widely used for the cooling of the infrared detector, and the alternatives of the helium in the Stirling cryocooler are nitrogen and hydrogen gas. In this study, the performance experiment of the small FPFD(Free Piston and Free Piston) type Stirling cooler and the moving coil type, dual acting linear compressor was performed when the nitrogen and helium is used for the working fluid The results show that the nitrogen refrigerant has small cooling capacity compared with the helium, but the performance characteristics of the linear compressor does not greatly changed.

• 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.

• Nuclear Engineering and Technology
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• 제51권6호
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• pp.1514-1524
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• 2019

Hydrogen-steam gas mixture may be injected into containment with flow regime varying both spatially and transiently due to wall effect and pressure difference between primary loop and containment in severe accidents induced by loss of coolant accident. Preliminary CFD analysis is conducted to gain information about the helium flow regime transition process from jet to buoyancy plume for forthcoming experimental study. Physical models of impinging jet and wall condensation are validated using separated effect experimental data, firstly. Then helium transportation is analyzed with the effect of jet momentum, buoyancy and wall cooling discussed. Result shows that helium distribution is totally dominated by impinging jet in the beginning, high concentration appears near gas source and wall where jet momentum is strong. With the jet weakening, stable light gas layer without recirculating eddy is established by buoyancy. Transient reversed helium distribution appears due to natural convection resulted from wall cooling, which delays the stratification. It is necessary to concern about hydrogen accumulation in lower space under the containment external cooling strategy. From the perspective of experiment design, measurement point should be set at the height of connecting pipe and near the wall for stratification stability criterion and impinging jet modelling validation.

• Nuclear Engineering and Technology
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• 제56권5호
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• pp.1679-1686
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• 2024

Graphite material plays an important role in nuclear reactors especially the high-temperature gas-cooled reactors (HTGRs) by its outstanding comprehensive nuclear properties. The structural integrity of graphite pebble fuel elements is the first barrier to core safety under any circumstances. The correct knowledge of the stiffness coefficient of the graphite pebble fuel element inside the reactor's core is significant to ensure the valid design and inherent safety. In this research, a vertical extrusion device was set up to measure the stiffness coefficient of the graphite pebble fuel element by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University in China. The stiffness coefficient equations of graphite pebble fuel elements at different temperatures are given (in a helium atmosphere). The result first provides the data on the high-temperature stiffness coefficient of pebbles in helium gas. The result will be helpful for the engineering safety analysis of pebble-bed nuclear reactors.

• 한국분말재료학회지
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• 제10권1호
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• pp.1-5
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• 2003

Nano-sized WC powders were synthesized by vapor phase reaction using the precusor of tungsten ethoxide under helium and hydrogen atmosphere. The phases of the powder were varied with reaction Bone and gas flow rate. The powder size was about 30nm in diameter, and the tungsten carbide powder was coated by carbon layer. The synthesis of nano-sized WC powders was promoted as the hydrogen gas flow rate became higher. Inversely, tungsten oxide was formed by increasing the flow rate of helium gas. The synthesized powders were analyzed by XRD, FE-SEM, carbon analyzer etc.

• Korean Chemical Engineering Research
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• 제57권3호
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• pp.368-371
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• 2019

Using first principles calculations we investigated the thermomechanical stability of spent nuclear fuels (SNF), especially how mechanical properties of $UO_2$, such as, bulk, shear and Young's moduli and Poisson's ratio vary through alpha-decay of U into Th with generation of He gas. Our results indicate that substitution of U by Th through alpha decay ($U_{1-x}Th_xO_2$) does not significantly affect the stability of the grain in a fuel matrix. In addition, we studied the transport properties of He in and boundaries of the $U_{1-x}Th_xO_2$ grain. Helium preferentially resides at the grain boundaries through diffusion. Our study can contribute to substantial reduction of environmentally risk and enhancement of our sustainability by safe control of radioactive materials.

• 한국진공학회지
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• 제16권2호
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• pp.153-159
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• 2007

KSTAR 장치의 저온 component에 헬륨을 공급하기 위한 헬륨라인은 크게 두 가지로 이루어져 있다. 냉동기에서 KSTAR 저온용기 외부까지의 트랜스퍼 라인과, 저온용기 내부의 헬륨라인이다. KSTAR 장치는 3가지 종류의 헬륨을 사용하여 각 저온 component를 냉각하는데, 초전도 자석 시스템과 버스라인에는 초임계 헬륨, 전류인입장치에는 액체 헬륨, 열차폐체에는 가스 헬륨을 공급한다. 저온용기 내부의 헬륨라인은 냉동기에서 저온용기 근처까지 연결된 배관을 저온용기 내부의 각 장치에 최단거리로 열손실 없이 설치하여 각 장치가 정상 작동하도록 하는데 그 목적이 있다. 저온용기 내부의 헬륨라인은 최대 20bar로 가압되는 운전시간 동안에 헬륨누설 없이 설치되어야 한다. 그리고 상온으로 부터의 복사열을 차단하기 위하여 다층절연제로 배관을 감싸주어야 하고 고전압 부분은 프리프레그 테잎으로 절연되어야 한다. 전기절연체는 세라믹과 스테인레스 스틸 튜브를 브레이징 접합 방법으로 연결하여 만들어진 것으론 배관과 배관, 배관과 저온 component간의 절연을 위해 사용되고, 헬륨라인과 동일하게 4.5K 초임계 헬륨온도에서 누설이 없어야 한다. 따라서 모든 전기절연체는 액체질소에 침전시켜 열충격을 가하고, 내부에 30 bar를 가압하여 진공 누설시험을 한다. 그리고 초전도 자석과 배관의 절연체로 사용되므로 15kV 고전압 절연 검사를 한다. 전기절연체의 세라믹 부분은 구조적 보강을 위하여 추가적으로 표면에 절연 작업을 한다. 현재 대부분의 저온용기 내부의 헬륨 라인은 설치 완료되어 있으며, 최종 검사가 진행 중이다.