• Title/Summary/Keyword: thermal reduction reactor.

Search Result 65, Processing Time 0.032 seconds

Comprehensive validation of silicon cross sections

  • Czakoj, Tomas;Kostal, Michal;Simon, Jan;Soltes, Jaroslav;Marecek, Martin;Capote, Roberto
    • Nuclear Engineering and Technology
    • /
    • v.52 no.12
    • /
    • pp.2717-2724
    • /
    • 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.

THERMALHYDRAULIC EVALUATIONS FOR A CANFLEX BUNDLE WITH NATURAL OR RECYCLED URANIUM FUEL IN THE UNCREPT AND CREPT CHANNELS OF A CANDU-6 REACTOR

  • Jun, Ji-Su
    • Nuclear Engineering and Technology
    • /
    • v.37 no.5
    • /
    • pp.479-490
    • /
    • 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.

Catalytic Technologies for Nitric Acid Plants N2O Emissions Control: In-Duct-Dependent Technological Options (질산제조 플랜트 N2O 제거용 촉매기술: 적용위치별 기술옵션)

  • Kim, Moon-Hyeon
    • Journal of Environmental Science International
    • /
    • v.21 no.1
    • /
    • pp.113-123
    • /
    • 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.

Study on uranium metalization yield of spent pressurized water reactor fuels and oxidation behavior of fission products in uranium metals (사용후핵연료의 우라늄 금속 전환율 측정 및 전환체 내 핵분열생성물의 산화거동 연구)

  • Choi, Ke Chon;Lee, Chang Heon;Kim, Won Ho
    • Analytical Science and Technology
    • /
    • v.16 no.6
    • /
    • pp.431-437
    • /
    • 2003
  • Metalization yield of uranium oxide to uranium metal from lithium reduction process of spent pressurized water reactor (PWR) fuels was measured using thermogravimetric analyzer. A reduced metal produced in the process was divided into a solid and a powder part, and each metalization yield was measured. Metalization yield of the solid part was 90.7~95.9 wt%, and the powder being 77.8~71.5 wt% individually. Oxidation behaviour of the quartemary alloy was investigated to take data on the thermal oxidation stability necessary for the study on dry storage of the reduced metal. At $600{\sim}700^{\circ}C$, weight increments of alloy of Mo, Ru, Rh and Pd was 0.40~0.55 wt%. Phase change on the surface of the alloy was started at $750^{\circ}C$. In particular, Mo was rapidly oxidized and then the alloy lost 0.76~25.22 wt% in weight.

A Study on Pill Temperature Control method and Hydrogen Production with 2-step Thermochemical Cycle Using Dish Type Solar Thermal System (접시형 태양열 시스템을 이용한 2단계 열화학 싸이클의 수소 생산과 PID 온도 제어 기법 연구)

  • Kim, Chul-Sook;Kim, Dong-Yeon;Cho, Ji-Hyun;Seo, Tae-Beom
    • Journal of the Korean Solar Energy Society
    • /
    • v.33 no.3
    • /
    • pp.42-50
    • /
    • 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.

Hot and average fuel sub-channel thermal hydraulic study in a generation III+ IPWR based on neutronic simulation

  • Gholamalishahi, Ramin;Vanaie, Hamidreza;Heidari, Ebrahim;Gheisari, Rouhollah
    • Nuclear Engineering and Technology
    • /
    • v.53 no.6
    • /
    • pp.1769-1785
    • /
    • 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.

Development of Fault Monitoring Technique for Agitator Driving System

  • Park, Gee-yong;Park, Byung-suk;Yoon, Ji-sup;Hong, Dong-hee;Jin, Jae-hyun
    • 제어로봇시스템학회:학술대회논문집
    • /
    • 2002.10a
    • /
    • pp.32.1-32
    • /
    • 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

  • PDF

A Study on Reaction Characteristics for NOx Reduction in Flue Gas Denitrification using Plasma (플라즈마 배연탈질에서 NOx 저감에 관한 반응제 특성 연구)

  • Baek, Hyun Chang;Shin, Dae Hyun;Woo, Je Kyung;Kim, Sang Guk;Kim, Dong Chan;Park, Yeong Seong
    • Journal of Korean Society of Environmental Engineers
    • /
    • v.22 no.12
    • /
    • pp.2247-2254
    • /
    • 2000
  • This study was carried out to investigate the reaction characteristics of NOx with reagents to grope the power consumption rate reduction and NOx removal rate improvement for the non-thermal plasma denitrification process. The experiments were performed using the real flue gas and wire-plate type plasma reactor. and the flow rate of real flue gas is $20Nm^3/hr$. Paraffinic and olefinic hydrocarbons and ammonia were used as reagents. Olefinic hydrocarbon oxidizes NO more actively than paraffinic hydrocarbon under the non-thermal plasma conditions, resulting in the generation of large amount of $NO_2$ and a very small amount of CO. When the initial NOx concentration increases. oxidation rate of NO decreases and the consumption rate of olefinic hydrocarbon increases significantly. On the other hand. $NH_3$ did not promote reduction reaction with NO under non-thermal plasma conditions. however, there was a tendency that the NHa was effective to remove the $NO_2$ oxidized by olefinic hydrocarbon.

  • PDF

Oxidation Characteristics of Low Concentration CO Gas by the Natural Manganese Dioxide(NMD) in a Fixed Bed (고정층 반응기에서 망간광석(NMD)을 이용한 저농도 일산화탄소 산화특성)

  • Lee, Young Soon;Park, Jong Soo;Oh, Kwang Joong
    • Clean Technology
    • /
    • v.2 no.1
    • /
    • pp.60-68
    • /
    • 1996
  • The oxidation of carbon monoxide of low concentration on the natural manganese dioxide (NMD) has been investigated in a fixed bed reactor. The experimental variables were concentration of oxygen (500ppm~99.8%) and carbon monoxide (500ppm~10000ppm) and catalyst temperature ($50{\sim}750^{\circ}C$). The NMD(Natural Manganese Dioxide) has been characterized by temperature - program reduction(TPR) using 2.4% $CO/H_2$ as a reducing agent, thermogravimetric analysis (TGA), and reduction of NMD by 2.4% $CO/H_2$. It was found that the NMD catalyst activity on the unit area was greater than the $MnO_2$ catalyst for oxidation of CO at the same temperature. The thermal stability of oxidation activity was considered to be maintained when the NMD was heated to $750^{\circ}C$. The TGA, reduction by CO, and TPR of the NMD showed that the NMD had active lattice oxygen which was easily liberated on heating in the absence and low concentration of oxygen. The reaction order in CO is 0.701 between 500~3500ppm and almost zero between 3500~10000ppm of CO.

  • PDF

Characterization of NOx Reduction on Filter Bag Support System at Low Temperature using Powder Type MnOx and V2O2/TiO2 Catalysts (분말형 MnOx와 V2O2/TiO2 촉매를 이용한 저온영역의 백필터 공정에서 질소산화물 제거 특성)

  • Kim, Byung-Hwan;Kim, Jeong-Heon;Kang, Pil-Sun;Yoo, Seung-Kwan
    • Journal of Korean Society for Atmospheric Environment
    • /
    • v.26 no.1
    • /
    • pp.1-9
    • /
    • 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.