• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2004.06a
• /
• pp.418-418
• /
• 2004

풀, 토양 또는 지하수와 같은 환경시료 중에 포함된 미량 우라늄을 분석하기 위하여 핵분열 트랙 기입법을 이용하였다. 시료 전처리 방법으로 지하수 시료는 질산 산성으로 만든 후, 토양시료는 질산과 불산을 이용하여 용액화 하였으며, 풀 시료는 전기로를 이용하여 회화한 후, 질산과 불산을 이용하여 용액화 하였다. 이 환경시료 전처리용액들을 각각 0.1mL를 0.9mL Collodion 분산용액에 섞은 후, 우라늄 표준용액과 함께 플라스틱 판($6{\times}6\textrm{cm}^2$) 위에 10$\mu\textrm{\ell}$씩 점적, 건고 시키고 핵분열 트랙기입법을 이용하여 우라늄 농도를 분석하였다. 핵분열 트랙기입법을 위한 중성자조사는 한국원자력연구소 하나로 연구용원자로(열중성자 선속: $2.7{\times}10^{13}n/\textrm{cm}^2{\cdot}sec^{-1}$)에서 10분간 하였으며, 6.25M NaOH 용액($60^{\circ}C$)을 이용하여 10분간 화학 에칭 하였다. 고체트랙검출기 표면에 생성된 핵분열 트랙들은 광학현미경과 image analyzer system을 이용하여 관찰하고 계수하였다. 시료와 같이 점적한 우라늄 표준용액을 이용하여 우라늄 농도에 대한 단위면적당 트랙 수의 상관관계를 구하였으며, 이를 이용하여 시료 내 우라늄 농도를 결정하였다. 본 실험의 결과에 대한 검증을 위하여 동일 시료용액을 분리관을 이용한 전처리 과정을 거친 후 ICP-MS를 이용하여 분석하였다. 우라늄의 선택적 분리를 위하여 U-TEVA 추출크로마토그래피 분리관을 이용하였다. 본 연구의 핵분열 트랙기입법을 이용하여 환경시료를 분석하는 방법은 일반적인 분광법을 이용할 경우, 문제가 되는 방해 원소의 분리를 위한 전처리 과정이 불필요한 장점을 가지고 있으며, 1ng 정도의 미량 우라늄을 분석할 수 있었고, ICP-MS 결과와 20% 오차 이내에서 일치하였다.

• The KSFM Journal of Fluid Machinery
• /
• v.10 no.2 s.41
• /
• pp.41-45
• /
• 2007

The shutoff unit was designed to provide rapid insertion of neutron absorbing material into the reactor core to shutdown the reactor quickly and also to withdraw the absorber slowly to avoid a log-rate trip. Four shutoff units were installed on the HANARO reactor but the half-core test facility was equipped with one shutoff unit. The reactor trip or shutdown is accomplished by four shutoff units by insertion of the shutoff rods. The shutoff rod(SOR) is actuated by a directly linked hydraulic cylinder on the reactor chimney, which is pressurized by a hydraulic pump. The rod is released to drop by gravity, when triplicate solenoid valves are de-energized to vent the cylinder. The hydraulic pump, pipe and air supply system are provided to be similar with the HANARO reactor. The shutoff rod drops for 647mm stroke within 1.13 seconds to shut down the reactor and it is slowly inserted to the full down position, 700mm, with a damping. We have conducted the drop test of the shutoff rod in order to show the performance and the structural integrity of operating system of the shutoff unit. The present paper deals with the 647mm drop time and the withdrawal time according to variation of the pool water temperature, the water level and the core flow.

• Journal of Radiation Protection and Research
• /
• v.33 no.3
• /
• pp.121-126
• /
• 2008

Radioactivities of the stack air effluents from the Advance Fuel Science Building (AFSB) at KAERI have been investigated and evaluated. In this AFSB, nuclear fuels for the HANARO research reactor have been fabricated and the advanced nuclear fuels have been studied. A stack air monitoring system has been continuously operating to monitor the stack air effluents from the facility to protect the environment. As the results of the periodical radioactivity measurement and both the gamma and alpha spectrometry for the millipore filters taken from the stack air monitor from January until March 2008, a trace amount of primordial $^{40}K$ and the short-lived decay products of natural borne $^{222}Rn$ and $^{220}Rn$ have been detected. However, the radioactivities have rapidly decayed to the level below the Minimum Detectable Activity (MDA) of the counting system. Therefore, it was evaluated that no uranium isotopes have been released to the atmosphere from the stack of the AFSB at KAERI.

• Proceedings of the Korean Vacuum Society Conference
• /
• 2011.08a
• /
• pp.171-171
• /
• 2011

헬륨냉동계통은 연구용 원자로인 하나로에서 냉중성자를 생산할 수 있도록 설치된 수조내기기 내의 감속재인 수소가 정상적으로 열 사이펀을 유지하기 위한 주요 계통이다. 헬륨냉동계통은 헬륨가스를 압축하는 헬륨 압축부분과 헬륨가스를 팽창시켜 저온을 생성시키는 헬륨 팽창부분으로 나누어진다. 헬륨 압축부분은 두 개의 스크류가 맞물려 회전하면서 약 1.05 bar(a)의 헬륨가스를 최대 13 bar(a)까지 압축시키는 압축기가 있으며, 헬륨 팽창부분인 냉동박스의 팽창 터빈은 self-acting gas bearing에 의해 구동되며, 저온모드 운전 시작시 헬륨 압축부분에서 일부의 가스는 팽창 터빈 축(shaft)으로 유입되어 회전속도가 서서히 증가하면서 고속으로 회전하여 극저온의 헬륨가스(14~18 K)를 생성하는 주요 기기이다. 헬륨을 팽창하는 부분인 냉동박스 내로 헬륨 압축가스를 유입하기 전에 압축된 헬륨가스 내 불순물의 순도를 분석하여 냉동박스의 주요 부품인 팽창터빈의 운전에 영향을 미치지 않는 것이 가장 중요하다. 따라서 헬륨 저압측에 헬륨가스 내 불순물 즉, 수소($H_2$), 수분($H_2O$), 질소($N_2$), 탄화수소류(CxHy) 및 오일(Oilaerosol) 등의 함량을 분석하기위해 가스 분석기가 설치되어 있으며, 냉동박스 내로 유입되기 전에 헬륨압축에서 순환되는 가스 내 불순물인 수분, 질소, 탄화수소류 및 오일은 10 vpm 이하이어야 하며, 수소 함량은 0.1 % 이내이어야 한다. 헬륨 압축부분에서 순환되는 가스의 불순물이 요구 조건에 만족하도록 헬륨 고압측과 헬륨 저압측에 cryogenic adsorber를 설치하여 가스 내 불순물을 제거하는 가스순도제어 작업을 수행해야 한다. cryogenic adsorber를 사용하기 위해서는 장치 내의 불순 가스를 공정진공도(1.33 X $10^{-3}$ mbar) 이하로 진공배기하는 작업이 매우 중요하다. 이는 계통의 헬륨가스가 오염되지 않도록 하는 것으로 cryogenic adsorber 내에는 액체질소를 충전하여 액체질소 온도에 노출된 활성탄층을 헬륨가스가 흐르면서 수분, 질소, 탄화수소류 및 오일 등이 제거된다. 이 논문에서는 헬륨냉동계통의 가스 순도 제어 작업을 통해 헬륨가스의 순도가 요구조건 이하로 만족하며, 팽창 터빈의 운전에 영향을 미치지 않음을 기술하고자 한다.

• Proceedings of the Korean Institute of Electrical and Electronic Material Engineers Conference
• /
• 2010.06a
• /
• pp.338-338
• /
• 2010

지난 20여년 동안 반도체 레이저 다이오드는 주로 CD (DVD) 픽업용 (파장: 640 nm 이하) 및 통신용 (파장 1550 nm) 광원 분야에서 집중적으로 개발되어 왔다. 그러나 기술의 개발과 더불어 파장조절이 비교적 자유로워지고 광출력이 증대 되면서 기존의 레이저 고유의 영역까지 그 응용분야기 확대되고 있고, 이에 따라 고출력 반도체 레이저 다이오드의 시장 규모도 꾸준히 증가되고 있는 상황이다. 고출력 반도체 레이저 다이오드는 발진 파장 및 광출력에 따라 다양한 분야에 응용되고 있으며, 특히 발진파장이 808 nm 인 고출력 레이저 다이오드의 경우 재료가공, 펌핑용 광원 (DPSSL, 광섬유 레이저), 의료, 피부미용 (점 제거), 레이저 다이오드 디스플레이 등 가장 다양한 응용분야를 가진 광원 중의 하나라고 할 수 있다. MBE(Molecular Beam Epitaxy)로 성장된 InAlAs 에피층 (epi-layer)을 사용하여 고출력을 갚는 레이저 다이오드를 제작함에 있어서, 에피층은 결함 (defect)이 없는 우수한 단결정이 요구되지만, 실제 결정 성장 과정에서는 성장온도와 Al 조성비 등의 성장 조건의 변화에 따라 전기적 광학적 특성 및 신뢰성에 큰 영향을 받는 것으로 보고되고 있다. 이에 본 연구에서는 DLTS (Deep Level Transient Spectroscopy) 방법을 이용하여 InAlAs 양자점 에피층의 깊은 준위 거동을 조사하였다. DLTS 측정 결과, 0.3eV 부근의 point defect과 0.57 ~ 0.70 eV 영역의 trap이 조사되었으며, 이는 갈륨 (Ga) vacancy와 산소 원자의 복합체에 기인한 결함으로 분석된다.

• Korean Chemical Engineering Research
• /
• v.58 no.1
• /
• pp.135-141
• /
• 2020

Although the graphene is regarded as a promising material for the electrode of the supercapacitor, its electrochemical performance is still less enough to satisfy the current demand raised in real applications. Here, using a home laser engraver, firstly we performed the prompt and selective reduction of the graphene oxide to produce multilayered and highly porous graphene maintaining high electrical conductivity. Subsequently, the resulting graphene was conformally deposited with pseudocapacitive thin VO_x using atomic layer deposition in order to enhance specific capacitance of graphene. We observed that various forms of VO_x exist in the VO_x/graphene hybrid through XPS analysis. The hybrid showed highly improved specific capacitance (~189 F/g) as compared to the graphene without VO_x. We expect that our approach is accepted as one of the alternatives to produce the graphene-based electrode for various energy storage devices.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.18 no.2_spc
• /
• pp.327-336
• /
• 2020

The high-flux advanced neutron application reactor (HANARO) is a research reactor with thermal power of 30 MW applied in various research and development using neutrons generated from uranium fission chain reaction. A degasifier tank is installed in the ancillary facility of HANARO. This facility generates gas pollutants produced owing to internal environmental factors. The degasifier tank is designed to maintain the gas contaminants below acceptable levels and is monitored using an analyzer in the gas sampling panel. If condensate water is generated and flows into the analyzer of the gas sampling panel, corrosion occurs inside the analyzer's measurement chamber, which causes failure. Condensate water is generated because of the temperature difference between the degasifier tank and analyzer when the gas flows into the analyzer. A heating system is installed between the degasifier tank and gas sampling panel to suppress condensate water generation and effectively remove the condensate water inside the system. In this study, we investigated the efficiency of the heating system. In addition, the variations in the pipe temperature and the amount of average condensate water were modeled using a wall condensation model based on the changes in the fluid inlet temperature, outside air temperature, and heating cable-setting temperature.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2005.06a
• /
• pp.21-29
• /
• 2005

The HANARO, a multi-purpose research reactor of 30 MWth open-tank-in-pool type, has been under normal operation since its initial criticality in February, 1995. Recently, ten years after the initial operation of the HANARO, one of the two primary cooling pumps was decontaminated for overhaul maintenance in 2004. Before decontamination exposure doserate and surface contamination level of primary cooling pump measured at 4 points. After final decontamination exposure doserate and surface contamination level of primary cooling pump remeasured by same method done before. It is easy to decontaminate the out side exposed surfaces of the pump, but it is difficult to approach the inside surface due to double volute installed in the casing. Therefore, a new decontamination facility has been developed to solve this problem. A concentrated de-contaminant (DX-300) is rotated in the closed pump casing by the impeller actuated by a temporary motor. Nuclide particles are removed by the emulsification effect of the de-contaminant and the surface contaminants are chemically removed from the pump by the corrosion and dissolution effect. The inside surfaces of the primary cooling pump have been decontaminated by using the facility. As results, the contamination level of the inside surfaces was maintained below the surface contamination limit.

• Progress in Medical Physics
• /
• v.9 no.1
• /
• pp.55-64
• /
• 1998

In recent, the demand of development of the high dose rate brachytherapy source increased for substitute for Co-60 source by iridium source, since the supplying Co-60 source is very depressed and the high dose rate brachytherapy sources are entirely imported from the abroad. This study investigated the exposure rates and isotropic dose distributions for the Ir-192 source produced from $\^$191/Ir(n,r)$\^$192/Ir by nuclear reactor in Korea Atomic Energy Research Institute. The activity of source was obtained an 1.012 Ci (the initial activity without encapsulation was 2,87Ci) by measurement with encapsuled stainless steel. The exposure rate of provided Ir-192 source was determined on 6.36 ${\pm}$ 0.147 Rm$^2$/h-GBq (2.350 ${\pm}$ 0.054 Rcm$^2$/mCi-hr) within ${\pm}$ 2.2% discrepancy with IC-10 ion chamber (0.14 cc) which was mounted on the acrylic jig to 5, 10 and 20 cm from the center of source. The calculated doses with 22 most significant spectrum lines were corrected with intrinsic efficiency of the germanium detector were compared to measured exposure dose rates within ${\pm}$3.8 % discrepancy. The authors confirmed the high dose rate Ir-192 source could be replaced the long decayed Co-60 source via investigation of the isotropic dose distributions in lateral, source axis and diagonal direction of source center are very closed to within 3% uncertainties. Especially, this exposure rate constant and isotropic dose distribution will be fundamental to build the high dose rate source and develop the computed therapy planning system.

• Nuclear Engineering and Technology
• /
• v.24 no.1
• /
• pp.40-51
• /
• 1992

One of the important irradiation performance characteristics of the silicide dispersion fuel element in research reactors is the diameteral increase resulting from fuel swelling. This paper, will attempt to develop a physical model for the fuel swelling, DFSWELL, by analyzing the basic irradiation behaviours and some experimental evidences. From the experimental evidences, it was shown that the volume changes in irradiated U$_3$Si-Al were strongly dependent on temperature and fission rate. The quantitative-amount of swelling for silicide fuel is estimated by considering temperature, fission rate, solid fission product build-up and gas bubble behavior. The swelling for the silicide fuel is comprised of three major components : i ) a volume change due to the formation of an interfacial layer between the fuel particle and matrix. ii ) a volume change due to the accumulation of gas bubble nucleation iii ) a volume change due to the accumulation of solid fission products The DFSWELL model which takes into account the above three major physical components predicts well the absolute magnitude of silicide fuel swelling in accordance with the power histories in comparison with the experimental data.