• 한국농림기상학회지
• /
• 제1권1호
• /
• pp.52-59
• /
• 1999

Vegetation canopy plays an important role in $CO_2$/$H_2$O exchange between the biosphere and the atmosphere by controlling leaf stomata. In this study, rice (Oryza sativa L.), a staple crop in Asia was investigated to formulate its single leaf model of photosynthesis and stomatal conductance. Photosynthesis and stomatal conductance were measured with a portable infrared gas analyzer system. Other plant and meteorological variables were also measured. To evaluate empirical constants in this biochemical leaf model, nonlinear least squares technique was used. The maximum catalytic activity of enzyme and the maximum rate of electron transport were $ 100\mu$㏖ $m^{-2}$ $s^{-1}$ and $140 \mu$㏖ m$^{-2}$ s$^{-1}$ (@ 35$^{\circ}C$), respectively. The empirical constants, m and b, associated with stomatal conductance model were 9.7 and $0.06 m^{-2}$ $s^{-1}$ , respectively. On a leaf scale, agreements between the modeled and the measured values of photosynthesis and stomatal conductance were on average within 20%, and the simulation of diurnal variation was also satisfactory On a canopy scale, the Simple Biosphere model(SiB2) was tested using the derived parameters. The modeled energy fluxes were compared against the micrometeorologically measured fluxes over a rice canopy. Agreements between the modeled and the measured values of net radiation, sensible heat and latent heat fluxes, and $CO_2$ flux (i.e., net canopy photosynthesis) were on average within 25%.

• 대한기계학회논문집B
• /
• 제34권3호
• /
• pp.219-228
• /
• 2010

텀블형 드럼 건조기의 적외선 건조 과정동안의 온도 및 수분량의 변화를 예측할 수 있는 2 차원 수학적 모델을 개발하였다. 본 모델에서는 건조대상 물질의 액체 수분의 이동과 건조공기의 유동 및 열전달을 고려하였다. 유체의 유동과 열전달 현상, 그리고 복사열전달은 유한체적법을 이용하여 해석하였다. 텀블 건조기의 2 차원 모델을 모사하기 위한 지배방정식을 소개한 후 적외선 히터, 히터의 온도, 그리고 가열 패턴에 따른 수치해석을 수행하였고, 적외선 히터를 도입함으로써 건조시간을 감소시킬 수 있음을 제시하였다.

• Nuclear Engineering and Technology
• /
• 제50권6호
• /
• pp.989-995
• /
• 2018

Argonne National Laboratory of the United States and Kharkov Institute of Physics and Technology (KIPT) of Ukraine have cooperated on the development, design, and construction of a neutron source facility. The facility was constructed at Kharkov, Ukraine, and its commissioning process is underway. The facility will be used for researches, producing medical isotopes, and training young nuclear specialists. The neutron source facility is designed with a provision to include a cryogenically cooled moderator system-a cold neutron source (CNS). This CNS provides low-energy neutrons, which will be used in the scattering experiment and material structures analysis. Cold neutron guides, coated with reflective material for the low-energy neutrons, will be used to transport the cold neutrons to the experimental site. The cold neutron guides would keep the cold neutrons within certain energy and angular space concentrated inside, while most of the gamma rays and high-energy neutrons are not affected by the cold neutron guides. For the KIPT design, the cold neutron guides need to extend several meters outside the main shield of the facility, and curved guides will also be used to remove the gamma and high-energy neutron. The neutron guides should be installed inside a shield structure to ensure an acceptable biological dose in the facility hall. Heavy concrete is the selected shielding material because of its acceptable performance and cost. Shield design analysis was carried out for the CNS guide hall. MCNPX was used as the major computation tool for the design analysis, with neutron and gamma dose calculated separately. Weight windows variance reduction technique was also used in the shield design. The goal of the shield design is to keep the total radiation dose below the $5.0{\mu}Sv/hr$ guideline outside the shield boundary. After a series of iterative MCNPX calculations, the shield configuration and parameters of CNS guide hall were determined and presented in this article.

• Nuclear Engineering and Technology
• /
• 제50권6호
• /
• pp.820-828
• /
• 2018

The growing nuclear threat has amplified the need for developing diverse and accurate nuclear forensics analysis techniques to strengthen nuclear security measures. The work presented here is part of a research effort focused on developing a methodology for reactor-type discrimination of weapons-grade plutonium. To verify the developed methodology, natural $UO_2$ fuel samples were irradiated in a thermal neutron spectrum at the University of Missouri Research Reactor (MURR) and produced approximately $20{\mu}g$ of weapons-grade plutonium test material. Radiation transport simulations of common thermal reactor types that can produce weapons-grade plutonium were performed, and the results are presented here. These simulations were needed to verify whether the plutonium produced in the natural $UO_2$ fuel samples during the experimental irradiation at MURR was a suitable representative to plutonium produced in common thermal reactor types. Also presented are comparisons of fission product and plutonium concentrations obtained from computational simulations of the experimental irradiation at MURR to the nondestructive and destructive measurements of the irradiated natural $UO_2$ fuel samples. Gamma spectroscopy measurements of radioactive fission products were mostly within 10%, mass spectroscopy measurements of the total plutonium mass were within 4%, and mass spectroscopy measurements of stable fission products were mostly within 5%.

• 한국항행학회논문지
• /
• 제8권2호
• /
• pp.98-104
• /
• 2004

지역 여건상 ILS나 VOR/DME 등 항행안전시설을 이용한 착륙이 곤란한 활주로에서는 조종사가 직접 눈으로 확인하여 착륙하는 선회비행방식이 이용되고 있는 실정이다. 본 논문에서는 김해공항 북측 활주로와 같이 항행안전시설을 설치하지 못하는 공항에 대하여 선회착륙하는 항공기가 악천후등으로 최종적으로 선회해야하는 지점을 발견하지 못하고 통과하여 사고가 발생하는 것을 막기 위하여 선회지점을 벗어난 지점에 무선전파의 전파막, 즉 마커신호로 조종사에게 위험신호를 알려주는 역할을 하는 장비를 개발하기로 한다. 이 경우 항공기에는 별도의 장비를 갖추지 않고 조종사가 별도의 조작을 하지 않아도 경보가 울리도록 하여 조종사의 부담을 최대한으로 줄여야 한다. 이를 만족하기 위해서 ILS의 구성장비로 사용중인 마커를 기반으로 하고, 현재 마커에 사용중인 송신기의 주파수 및 변조방식등을 그대로 이용하고, 변조주파수 및 신호만을 바꾸고, 안테나를 특수한 형태로 개발하기로 한다. 또한 안테나의 방사패턴의 크기를 시뮬레이션하고, 경보후의 비행경로를 계산하여 시스템의 유효성을 검증한다.

• Nuclear Engineering and Technology
• /
• 제53권10호
• /
• pp.3236-3246
• /
• 2021

Lessons learned from the Fukushima Daiichi nuclear power plant accident directed that multiple failures should be considered more seriously rather than single failure in the licensing bases and safety cases because attempts to take accident management measures could be unsuccessful under the high radiation environment aggravated by multiple failures, such as complete loss of electric power, uncontrollable loss of coolant inventory, failure of essential safety function recovery. In the case of the complete loss of electric power called station blackout (SBO), if there is no mitigation action for recovering safety functions, the reactor core would be overheated, and severe fuel damage could be anticipated due to the failure of the active heat sink. In such a transient condition at CANDU-6 plants, the seal failure of the primary heat transport (PHT) pumps can facilitate a consequent increase in the fuel sheath temperature and eventually lead to degradation of the fuel integrity. Therefore, it is necessary to specify the regulatory guidelines for multiple failures on a licensing basis so that licensees should prepare the accident management measures to prevent or mitigate accident conditions. In order to explore the efficiency of implementing accident management strategies for CANDU-6 plants, this study proposed a realistic accident analysis approach on the SBO transient with multiple-failure sequences such as seal failure of PHT pumps without operator's recovery actions. In this regard, a comparative study for two PHT pump seal failure modes with and without coolant seal leakage was conducted using a best-estimate code to precisely investigate the behaviors of thermal-hydraulic parameters during transient conditions. Moreover, a sensitivity analysis for different PHT pump seal leakage rates was also carried out to examine the effect of leakage rate on the system responses. This study is expected to provide the technical bases to the accident management strategy for unmitigated transient conditions with multiple failures.

• Nuclear Engineering and Technology
• /
• 제54권7호
• /
• pp.2748-2754
• /
• 2022

Because existing reactant coolant system (RCS) leakage detection mechanisms are insensitive to small leaks, a real-time, direct detection system with a detection threshold below 0.5 gpm·hr^-1 was studied. A beta-ray detection system using a silicon detector with good energy resolution for beta rays and a low gamma-ray response was proposed. The detection performance in the leakage condition was evaluated through experiments and simulations. The concentration of ¹⁶N in the coolant corresponding to a coolant leakage of 0.5 gpm was calculated using the analytic method and ORIGEN-ARP. Based on the concentration of ¹⁶N and the measurement of the silicon detector with ⁹⁰Sr/⁹⁰Y, the beta-ray count rate was estimated using MCNPX. To evaluate the effect of gamma rays inside the containment building, the signal-to-noise ratio (SNR) was calculated. To evaluate the count rate ratio, the radiation field inside the containment building was simulated using MCNPX, and response evaluation experiments were performed using beta and gamma rays on the silicon detector. The expected beta-ray count rate at 0.5 gpm leakage was 7.26 × 10⁵ counts/sec, and the signal-to-background count rate ratio exceeded 88 for a transport time of 10 s, demonstrating its suitability for operation inside a reactor containment building.

• Nuclear Engineering and Technology
• /
• 제55권5호
• /
• pp.1734-1741
• /
• 2023

This work presents the synthesis and preparation of a new glass system described by the equation of (70-x) B₂O₃-5TeO₂ -20SrCO₃-5ZnO -xBi₂O₃, x = 0, 1, 5, 10, and 15 mol. %, using the melt quenching technique at a melting temperature of 1100 ℃. The photon-shielding characteristics mainly the linear attenuation coefficient (LAC) of the prepared glass samples were evaluated using Monte Carlo (MC) simulation N-particle transport code (MCNP-5) at gamma-ray energy extended from 59 keV to 1408 keV emitted by the radioisotopes Am-241, Ba-133, Cs-137, Co-60, Na-22, and Eu-152. Furthermore, we observed that the Bi₂O₃ content of the glasses had a significantly stronger impact on the LAC at 59 and 356 keV. The study of the lead equivalent thickness shows that the performance of fabricated glass sample with 15 mol.% of Bi₂O₃ is four times less than the performance of pure lead at low gamma photon energy while it is enhanced and became two times lower the perforce of pure lead at high energy. Therefore, the fabricated glasses special sample with 15 mol.% of Bi₂O₃ has good shielding properties in low, intermediate, and high energy intervals.

• 한국작물학회지
• /
• 제52권1호
• /
• pp.69-80
• /
• 2007

태양광과 반응하여 독특한 광화학적 작용을 하는 이산화티탄($TiO_2$)을 벼 잎 표면에 처리하였을 때 벼 엽신의 광합성 대사에 대한 영향을 검토하고 프로테옴 분석을 통해 생리변화를 구명하고자 수행한 결과를 요약하면 다음과 같다. 1. 광합성유효파장이 $2,400\;{\mu}mol\;m^{-2}\;s^{-1}$과 $2,200\;{\mu}mol\;m^{-2}\;s^{-1}$ 배치구에서 이산화티탄 10, 20 ppm 처리는 광적응상태의 엽록소형광지수(Yield)를 낮추었고 $450\;{\mu}mol\;m^{-2}\;s^{-1}$ 처리구는 엽록소형광지수를 높였다. 2. 노지조건인 PAR $2,400\;{\mu}mol\;m^{-2}\;s^{-1}$ 배치구에서 광합성 명반응의 상대전자전달율은 이산화티탄 10 ppm 처리에서 평균 45 %, 무처리 32.4 %, diuron 10 ppm 처리구에서 15.3%로 이산화티탄 처리는 광합성 명반응의 상대전자전달율을 높였다. 3. UV-B 4.9, $0.6\;KJ\;m^{-2}\;day^{-1}$ 배치구에서 이산화티탄 처리로 초장이 증가하였고 UV-B $0.15\;KJ\;m^{-2}\;day^{-1}$ 배치구에서 초장은 증가하고 건물중은 감소하였다. 4. 광합성은 노지의 UV-B 조건인 $13.6\;KJ\;m^{-2}\;day^{-1}$ 배치구에서 이산화티탄 처리로 종가하였고 UV-B 4.9, 0.6, $0.15\;KJ\;m^{-2}\;day^{-1}$ 배치구는 다소 증가하였으나 통계적으로 유의한 차이는 나타내지 않았다. 5. 이산화티탄 처리 후 자연광 중의 UV-B를 99% 차단하여 저수준으로 조절한 결과 68%의 단백질 발현이 감소하였고 각각 16%의 단백질 발현이 증가 또는 신생 합성되었다. 6. 이산화티탄 20 ppm 처리 후 자연광 중의 UV-B를 99% 차단시켰을 때 주로 광합성 Calvin cycle에서 $CO_2$ 결합을 촉매하는 결정구조 Rubisco의 chain E 발현이 감소하였다.

• 한국의학물리학회지:의학물리
• /
• 제11권2호
• /
• pp.117-122
• /
• 2000

해상도가 뛰어나며 디지털영상으로 저장하므로 공간에 제약을 받지 않으며 재사용이 가능하다는 장점으로 현재 국내 병원에서는 Imaging Plate(IP)가 필름을 대체해가고 있는 추세에 있다. 본 연구는 진단용으로 사용되는 If를 이용하여 치료영역에서 선량측정용도로의 가능성 여부를 알아보고자 하였다. 실험을 하는데 사용되었던 IP는 Fuji사의 ST-V$_{A}$라는 모델이고 가속기는 Varian 2100C의 6 MV 광자선을 사용하였다. 먼저 전리함으로 측정한 심부선량을 기준으로 If로 측정한 값과 비교를 하였다. 조사문 선량(portal dose)을 측정하기 위하여 SSD=100 cm 위치에 두께 14 cm 되는 폴리스틸렌 팬텀을 놓고 그 밑에 전자포탈영상기구(Electronic Portal Imaging Device: EPID)가 위치한 지점에서 상대적 흡수선량(Off Axis Ratio: OAR)을 측정 그리고 계산하였다. 이때 전리함, 필름(Kodak X-Omat V) 및 IP를 전자포탈영상기구와 같은 위치에 놓고 측정을 하였고 이에 더하여 EGS4 몬테칼로전산모사를 통하여 조사문 선량을 계산하였다. 심부선량(PDD)을 측정한 결과 IP는 BaFBr:Eu$^{2+}$의 인광물질로 이루어져 있기 때문에 물보다 전자밀도가 높아 산란선에 매우 민감함을 알 수 있었다. 따라서 현재 진단영역에서 사용되고있는 IP는 심부선량측정계로는 적합하지 않다. 그러나 IP는 반음영외부부분(outside penumbra)을 제외한 조사문 선량측정에 비교적 정확한 것으로 밝혀졌다 또한 IP를 치료위치 확인용으로 사용할 수 있을 것으로 기대된다.