• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2717-2724
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• 2020

Silicon, especially silicon in the form of SiO₂, is a major component of rocks. Final spent fuel storages, which are being designed, are located in suitable rock formations in the Earth's crust. Reduction of the uncertainty of silicon neutron scattering and capture is needed; improved silicon evaluations have been recently produced by the ORNL/IAEA collaboration within the INDEN project. This paper deals with the nuclear data validation of that evaluation performed at the LR-0 reactor by means of critical experiments and measurement of reaction rates. Large amounts of silicon were used both as pure crystalline silicon and SiO₂ sand. The critical moderator level was measured for various core configurations. Reaction rates were determined in the largest core configuration. Simulations of the experimental setup were performed using the MCNP6.2 code. The obtained results show the improvement in silicon cross-sections in the INDEN evaluations compared to existing evaluations in major libraries. The new Thermal Scattering Law for SiO₂ published in ENDF/B-VIII.0 additionally reduces the discrepancy between calculation and experiments. However, an unphysical peak is visible in the neutron spectrum in SiO₂ obtained by calculation with the new Thermal Scattering Law.

• Nuclear Engineering and Technology
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• 제37권5호
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• pp.479-490
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• 2005

The thermalhydraulic performance of a CANDU-6 reactor loaded with various CANFLEX fuel bundles is evaluated by the NUCIRC code, which is incorporated with recent models of pressure drop and critical heat flux (CHF) predictions based on high-pressure steam-water tests for the CANFLEX bundle as well as a 37-element bundle. The distributions of channel flow rate, channel exit quality, critical channel power (CCP), and critical power ratio (CPR) for the CANFLEX bundles (with natural or recycled uranium fuel) in the CANDU-6 reactor fuel channel are calculated by the code. The effects of axial and radial heat flux on CCP are evaluated by assuming that the recycled uranium fuel (CANFLEX-RU) has the same geometric data as the natural uranium fuel bundle (CANFLEX-NU), but a different power distribution due to different fuel composition and refueling scheme. In addition, the effects of pressure tube creep and bearing-pad height are examined by comparing various results of uncrept, and $3.3\%\;and\;5.1\%$ crept channels loaded with CANFLEX bundles with 1.4 mm or 1.7 mm high bearing-pads with those of the 37-element bundle. The distributions of the channel flow rate and CCP for the CANFLEX-NU or -RU bundle show a typical trend for a CANDU-6 reactor channel, and the CPRs are maintained above at least 1.444 (NU) or 1.455 (RU) in the uncrept channel. The enhanced CHF of the CANFLEX bundle (particularly with 1.7mm height bearing-pads) produces a higher thermal margin and considerably less sensitivity to CCP reduction due to the pressure tube creep than the 37-element bundle. The CCP enhancement due to the raised bearing-pads is estimated to be about $3\%\~5\%$ for the CANFLEX-NU and $2\%\~6\%$ for the CANFLEX-RU bundle, respectively.

• 한국환경과학회지
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• 제21권1호
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• pp.113-123
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• 2012

A unit emission reduction of nitrous oxide ($N_2O$) from anthropogenic sources is equivalent to a 310-unit $CO_2$ emission reduction because the $N_2O$ has the global warming potential (GWP) of 310. This greatly promoted very active development and commercialization of catalysts to control $N_2O$ emissions from large-scale stationary sources, representatively nitric acid production plants, and numerous catalytic systems have been proposed for the $N_2O$ reduction to date and here designated to Options A to C with respect to in-duct-application scenarios. Whether or not these Options are suitable for $N_2O$ emissions control in nitric acid industries is primarily determined by positions of them being operated in nitric acid plants, which is mainly due to the difference in gas temperatures, compositions and pressures. The Option A being installed in the $NH_3$ oxidation reactor requires catalysts that have very strong thermal stability and high selectivity, while the Option B technologies are operated between the $NO_2$ absorption column and the gas expander and catalysts with medium thermal stability, good water tolerance and strong hydrothermal stability are applicable for this option. Catalysts for the Option C, that is positioned after the gas expander thereby having the lowest gas temperatures and pressure, should possess high de$N_2O$ performance and excellent water tolerance under such conditions. Consequently, each de$N_2O$ technology has different opportunities in nitric acid production plants and the best solution needs to be chosen considering the process requirements.

• 분석과학
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• 제16권6호
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• pp.431-437
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• 2003

가압경수로 사용후핵연료 (이산화 우라늄)의 리튬환원공정으로부터 생산된 우라늄 금속 전환체에 대한 금속 전환율을 건식방법인 열중량분석법 (T.G.A)으로 측정하였다. 전환체를 고체와 분말로 분류하여 측정한 결과 우라늄 금속 전환율은 각각 90.7~95.9 및 77.8~71.5 wt% 이었다. 금속 전환체의 건식저장 시 열적 산화 안정성을 확인하기 위하여 전환체내에 함유되어 있는 Mo, Ru, Rh 및 Pd 합금에 대한 산화 거동을 조사하였다. 합금을 $600{\sim}700^{\circ}C$의 공기분위기에서 산화시킨 결과 0.40~0.55 wt%의 무게증가를 보였으며 $750^{\circ}C$부터는 표면으로부터 산화가 진행되어 상변화가 일어났다. $900^{\circ}C$에서는 Mo의 휘발에 의한 영향으로 0.76~25.22 wt%의 무게 감소를 나타내었다.

• 한국태양에너지학회 논문집
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• 제33권3호
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• pp.42-50
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• 2013

Solar thermal reactor was studied for hydrogen production with a two step thermochemical cycle including T-R(Thermal Reduction) step and W-D(Water Decomposition) step. NiFe2O4 and Fe3O4 supported by monoclinic ZrO2 were used as a catalyst device and Ni powder was used for decreasing the T-R step reaction temperature. Maintaining a temperature level of about $1100^{\circ}C$ and $1400^{\circ}C$, for 2-step thermochemical reaction, is important for obtaining maximum performance of hydrogen production. The controller was designed for adjusting high temperature solar thermal energy heating the foam-device coated with nickel- ferrite powder. A Pill temperature control system was designed based on 2-step thermochemical reaction experiment data(measured concentrated solar radiation and the temperature of foam device during experiment). The cycle repeated 5 times, ferrite conversion rate are 4.49~29.97% and hydrogen production rate is 0.19~1.54mmol/g-ferrite. A temperature controller was designed for increasing the number of reaction cycles related with the amount of produced hydrogen.

• Nuclear Engineering and Technology
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• 제53권6호
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• pp.1769-1785
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• 2021

The Integral Pressurized Water Reactors (IPWRs) as the innovative advanced and generation-III + reactors are under study and developments in a lot of countries. This paper is aimed at the thermal hydraulic study of the hot and average fuel sub-channel in a Generation III + IPWR by loose external coupling to the neutronic simulation. The power produced in fuel pins is calculated by the neutronic simulation via MCNPX2.6 then fuel and coolant temperature changes along fuel sub-channels evaluated by computational fluid dynamic thermal hydraulic calculation through an iterative coupling. The relative power densities along the fuel pin in hot and average fuel sub-channel are calculated in sixteen equal divisions. The highest centerline temperature of the hottest and the average fuel pin are calculated as 633 K (359.85 ℃) and 596 K (322.85 ℃), respectively. The coolant enters the sub-channel with a temperature of 557.15 K (284 ℃) and leaves the hot sub-channel and the average sub-channel with a temperature of 596 K (322.85 ℃) and 579 K (305.85 ℃), respectively. It is shown that the spacer grids result in the enhancement of turbulence kinetic energy, convection heat transfer coefficient along the fuel sub-channels so that there is an increase in heat transfer coefficient about 40%. The local fuel pin temperature reduction in the place and downstream the space grids due to heat transfer coefficient enhancement is depicted via a graph through six iterations of neutronic and thermal hydraulic coupling calculations. Working in a low fuel temperature and keeping a significant gap below the melting point of fuel, make the IPWR as a safe type of generation -III + nuclear reactor.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 2002년도 ICCAS
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• pp.32.1-32
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• 2002

The fault monitoring technique is presented for identifying the status of the agitator driving system in thermal reduction reactor. For identifying a fault such as bearing defect or clearance blocking, Wavelet transform (WT) is applied to vibration signals and features are extracted. For classification, the fuzzy ARTMAP is employed. With the features from WT, a single training epoch and a single learning iteration are sufficient for the fuzzy ARTMAP to classify the faults. The test results show the perfect classification though some features extracted from the test data are distorted against those in the training data

• 대한환경공학회지
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• 제22권12호
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• pp.2247-2254
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• 2000

본 연구는 저온 플라즈마 탈질 기술의 전력소모량 절감과 처리율 향상을 모색하고자 저온 플라즈마 조건에서 NOx와 반응제의 반응 특성을 고찰하였다. 실험은 $20Nm^3/hr$의 실제 배가스와 wire-plate type 플라즈마 반응기를 이용하여 진행되었으며, 반응제로는 파라핀계와 올레핀계 탄화수소 및 $NH_3$를 사용하였다. 저온 플라즈마 조건에서 올레핀계 탄화수소는 파라핀계 탄화수소에 비하여 NO의 산화에 탁월한 효과를 보여 다량의 $NO_2$를 생성할 뿐만 아니라 미량의 CO도 생성하였다. 또한 NOx의 초기농도가 높아지면 NO의 산화율은 감소할 뿐만 아니라 올레핀계 탄화수소의 소모량도 두드러진 증가를 보였다. 한편 $NH_3$은 저온 플라즈마 조건에서 NO와의 환원반응이 촉진되지 않았지만 올레핀계 탄화수소에 의하여 산화된 $NO_2$의 제거에는 효과적인 경향을 보였다.

• 청정기술
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• 제2권1호
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• pp.60-68
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• 1996

고정층 반응기에서 망간광석을 이용하여 저농도의 일산화탄소 산화제어반응에 대하여 고찰하였다. 고려된 실험변수는 일산화탄소 농도 (500ppm~10000ppm), 산소 농도(500ppm~99.8%)와 촉매의 온도($50{\sim}750^{\circ}C$)이다. 또한 망간광석의 특성은 Thermogravimetric Analysis(TGA), 일산화탄소에 의한 환원, Temperature Programmed Reduction(TPR)실험을 이용하여 규명하였다. 망간광석의 일산화탄소 산화력은 순수이산화망간에 비해서 단위 면적당 높은 산화력과 $750^{\circ}C$까지 가열된 후에도 산화력이 유지될 수 있는 안정된 촉매작용을 보였다. Temperature Programmed Desorption(TPD), TPR 실험과 TG 등의 분석결과 산소의 농도가 낮거나 무산소하에서 망간광석의 격자내 산소가 쉽게 제공될 수 있음을 알 수 있었다. 일산화탄소의 농도가 500~3500ppm일 때 일산화탄소의 반응차수는 0.701이며 3500~10000ppm구간에서 일산화탄소의 농도에 무관한 0차 반응이었다.

• 한국대기환경학회지
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• 제26권1호
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• pp.1-9
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• 2010

In this study, the selective catalytic reduction of $NO_x$ with ammonia was carried out in a filter bag support reactor. The experiments were performed by powder type $MnO_x$ and $V_2O_5$/$TiO_2$ catalyst at low temperature between 130 and $250^{\circ}C$. Also, the effect of $SO_2$ and $H_2O$ on the NO conversion was investigated under our test conditions. The powder type catalysts were analyzed by X-ray photoelectron spectrum (XPS), X-ray diffraction(XRD), scanning electron microscopy (SEM) and thermal gravimetric analysis (TGA). It was observed that NO removal efficiency of the powder type $V_2O_5$/$TiO_2$ catalyst was 85% at low temperature($200^{\circ}C$) under presence of oxygen and that of $MnO_x$ was 50% at the same condition. The powder type $V_2O_5$/$TiO_2$ catalyst, in conclusion, was found to be available for SCR reaction in a filter bag support system.