• 제목/요약/키워드: high temperature reactors

검색결과 206건 처리시간 0.028초

연료가스의 고온 탈황에 사용된 Zinc Titanate의 재생 (Regeneration of Zinc Titanate Used for High Temperature Desulfurization of Fuel Gases)

  • 이태진;권원태
    • 에너지공학
    • /
    • 제7권1호
    • /
    • pp.73-80
    • /
    • 1998
  • Zinc titanate 탈황제를 제조하여 연료가스의 고온탈황에 사용된 탈황제의 재생에 대해서 연구하였다. 준비된 탈황제의 Zn/Ti 몰비는 1.5이고 반응기는 내경 1 cm와 3 cm의 석영관 고정층반응기들을 사용하였다. 고온에서 zinc titanate 탈황제의 재생은 발열반응을 수반하여 탈황제의 물성을 저하시킨다. 따라서 zinc titanate 탈황제의 가장 적합한 재생조건을 선정하기 위해서 반응온도, 산소함량, 유량변화, steam 함량 등을 변화시키면서 재생반응을 실험하였다. 탈황-재생의 실험동안 H2S와 SO2의 파과곡선을 구하였다. 또한 반응실험 전후의 탈황제의 물성을 SEM, XRD, Hg-porosimetry 및 BET로 분석하였다. 이런 결과들로부터 zinc titanate 탈황제에 가장 적합한 재생조건은 $650^{\circ}C$, O2 함? 5%, steam 함량 10% 이상이라는 결론을 얻었다.

  • PDF

화학증착법을 이용한 삼중 코팅 핵연료 제조에 관한 연구 (A Study on the CVD Deposition for SiC-TRISO Coated Fuel Material Fabrication)

  • 김준규;금이슬;최두진;김성순;이홍림;이영우;박지연
    • 한국세라믹학회지
    • /
    • 제44권3호
    • /
    • pp.169-174
    • /
    • 2007
  • TRISO coated fuel particle is one of the most important materials for hydrogen production using HTGR (high temperature gas cooled reactors). It is composed of three isotropic layers: inner pyrolytic carbon (IPyC), silicon carbide (SiC), outer pyrolytic carbon (OPyC) layers. In this study, TRISO coated fuel particle layers were deposited through CVD process in a horizontal hot wall deposition system. Also the computational simulations of input gas velocity, temperature profile and pressure in the reaction chamber were conducted with varying process variable (i.e temperature and input gas ratios). As deposition temperature increased, microstructure, chemical composition and growth behavior changed and deposition rate increased. The simulation showed that the change of reactant states affected growth rate at each position of the susceptor. The experimental results showed a close correlation with the simulation results.

고분자 전해질 연료전지 적용을 위한 DME 자열개질가스 내 CO제거 공정 특성 연구 (Experiment of CO Cleaning Process in DME Autothermal Reformate Gas for PEMFC Application)

  • 최승현;배중면
    • 한국수소및신에너지학회논문집
    • /
    • 제22권4호
    • /
    • pp.474-480
    • /
    • 2011
  • Hydrocarbon is required to be converted to pure hydrogen without carbon monooxide (CO) for polymer exchange membran fuel cell (PEMFC) applications. In this paper, CO cleaning processes as the downstream of Dimethyl ehter (DME) autothermal reforming process were performed in micro-reactors. Our study suggested two kinds of water gas shift (WGS) reaction process: High Temperature shift (HTS) - Low Temperature shift (LTS), Middle temperature shift (MTS). Firstly, using perovskite catalyst for MTS was decreased effieiciency since methanation. Using HTS-LTS the CO concentration was decreased about 2% ($N_2$ & $H_2O$ free) with the reaction temperature of $420^{\circ}C$ and $235^{\circ}C$ for HTS and LTS, respectively. As the final stage of CO cleaning process, preferential oxidation (PROX) was applied. The amount of additional oxygen need 2 times of stoichiometric at $65^{\circ}C$. The total conversion reforming efficiency of 75% was gained.

A MIXED CORE FOR SUPERCRITICAL WATER-COOLED REACTORS

  • Cheng, Xu;Liu, Xiao-Jing;Yang, Yan-Hua
    • Nuclear Engineering and Technology
    • /
    • 제40권2호
    • /
    • pp.117-126
    • /
    • 2008
  • In this paper, a new reactor core design is proposed on the basis of a mixed core concept consisting of a thermal zone and a fast zone. The geometric structure of the fuel assembly of the thermal zone is similar to that of a conventional thermal supercritical water-cooled reactor(SCWR) core with two fuel pin rows between the moderator channels. In spite of the counter-current flow mode, the co-current flow mode is used to simplify the design of the reactor core and the fuel assembly. The water temperature at the exit of the thermal zone is much lower than the water temperature at the outlet of the pressure vessel. This lower temperature reduces the maximum cladding temperature of the thermal zone. Furthermore, due to the high velocity of the fast zone, a wider lattice can be used in the fuel assembly and the nonuniformity of the local heat transfer can be minimized. This mixed core, which combines the merits of some existing thermal SCWR cores and fast SCWR cores, is proposed for further detailed analysis.

이중냉각연료에서 지지격자의 압력손실에 대한 엔탈피 증가 (Enthalpy Rise for Pressure Loss of Spacer Grids of Dual Coolant Fuel)

  • 전건호;전태현;신창환
    • 대한기계학회:학술대회논문집
    • /
    • 대한기계학회 2007년도 춘계학술대회B
    • /
    • pp.3473-3478
    • /
    • 2007
  • A dual side cooling annular fuel having internal and external coolant channels has many advantages basically due to low fuel temperature and high DNBR margin, which can make a significant increase of core power density possible. So recently a 12x12 square annular fuel array was proposed for the fuel assembly to be reloaded without structural interference with operating reactors of OPR-1000s. Even through the inherent potential of the annular fuel on the high power density, it may be seriously eroded in the case of a severe unbalanced mass flux split to the internal and external channels in standpoint of DNB. Mass flux split is determined pressure drop characteristics between inner and outer channels. The spacer grids binding fuel array influence greatly the pressure drop in outer channels and the mass flux split. As an important factor of DNB behavior, the enthalpy differences at both channel exits were evaluated using the mass flux splits.

  • PDF

Nuclear Corrosion: Achievements and Challenges

  • Feron, Damien
    • Corrosion Science and Technology
    • /
    • 제15권3호
    • /
    • pp.113-119
    • /
    • 2016
  • Corrosion science faces new challenges in various nuclear environments. Three main areas may be identified where increases of knowledge and understanding have been done and are still needed to face the technical needs: (i) the extension of the service time of nuclear power plants from 40 years, as initially planned, to 60 years and probably more as expected now, (ii) the prediction of long term behaviour of metallic materials in nuclear waste disposal where the corrosion processes have to be predicted over large periods of time, some thousands years and more, (iii) the choice of materials for use at very high temperatures as expected in Generation IV power plants in environments like gas (helium), supercritical water, liquid metals or salts. Service time extension, deep geological waste repositories and high temperature reactors sustain researches and developments to model corrosion phenomena at various scales, from atoms to components.

고농도 암모니아성 폐수의 질산화과정에서 아질산염 축적의 영향인자 (Factors Influencing Nitrite Build-up Nitrification of High Strength Ammonia Wastewater)

  • 한동준;강성환;임재명
    • 환경위생공학
    • /
    • 제13권2호
    • /
    • pp.128-138
    • /
    • 1998
  • This study was focused to find how each factors effect on the biological nitrification in wastewater treatment under high ammonia nitrogen concentration. Batch reactors in aerobic conditions were used to test the treatment efficiency of mixed liquor, nightsoil and piggery wastewater. The results are summeried as follows; Initial ammonia nitrogen concentration and pH were the direct influencing factors of nitrite build-up. More than 250 mg NH$_{4}$$^{+}$ - N/L in initial concentration built up nitrite and then the inhibition rate to Nitrobacter was above 70 percentage. And maximum nitritation rate was showed at pH 8.3 and nitrification could be completely achieved by pH control. Temperature and dissolved oxygen were the indirect influencing factors of nitrite build-up. These were a great effect on the activity of nitrifying microbes and ammonia nitrogen removal. Maximum nitritation rate was showed at 30 $\circ $C. The effect of DO concentration was negligible at more than 3 mg/L.

  • PDF

Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing

  • Lee, Tae Hyun;Ryu, Kyung Ha;Kim, Hong Deok;Hwang, Il Soon;Kim, Ji Hyun;Lee, Min Ho;Choi, Sungyeol
    • Nuclear Engineering and Technology
    • /
    • 제51권5호
    • /
    • pp.1381-1389
    • /
    • 2019
  • Stress corrosion cracking (SCC) widely found in both primary and secondary sides of steam generator (SG) tubing in pressurized water reactors (PWR) has become an important safety issue. Using eddy-current tests (ECTs), non-destructive evaluations are performed for the integrity management of SG tubes against intergranular SCC. To enhance the reliability of ECT, this study investigates the effects of oxide films on ECT's detection capabilities for SCC in laboratory-degraded SG tubing in high temperature and high pressure aqueous environment.

Flow regime transition criteria for vertical downward two-phase flow in rectangular channel

  • Chalgeri, Vikrant Siddharudh;Jeong, Ji Hwan
    • Nuclear Engineering and Technology
    • /
    • 제54권2호
    • /
    • pp.546-553
    • /
    • 2022
  • Narrow rectangular channels are employed in nuclear research reactors that use plate-type nuclear fuels, high heat-flux compact heat exchangers, and high-performance micro-electronics cooling systems. Two-phase flow in narrow rectangular channels is important, and it needs to be better understood because it is considerably different than that in round tubes. In this study, mechanistic models were developed for the flow regime transition criteria for various flow regimes in co-current air-water two-phase flow for vertical downward flow inside a narrow rectangular channel. The newly developed criteria were compared to a flow regime map of downward air-water two-phase flow inside a narrow rectangular channel with a 2.35-mm gap width under ambient temperature and pressure conditions. Overall, the proposed model showed good agreement with the experimental data.

Role of Radio Frequency and Microwaves in Magnetic Fusion Plasma Research

  • Park, Hyeon K.
    • Journal of electromagnetic engineering and science
    • /
    • 제17권4호
    • /
    • pp.169-177
    • /
    • 2017
  • The role of electromagnetic (EM) waves in magnetic fusion plasma-ranging from radio frequency (RF) to microwaves-has been extremely important, and understanding of EM wave propagation and related technology in this field has significantly advanced magnetic fusion plasma research. Auxiliary heating and current drive systems, aided by various forms of high-power RF and microwave sources, have contributed to achieving the required steady-state operation of plasmas with high temperatures (i.e., up to approximately 10 keV; 1 eV=10000 K) that are suitable for future fusion reactors. Here, various resonance values and cut-off characteristics of wave propagation in plasmas with a nonuniform magnetic field are used to optimize the efficiency of heating and current drive systems. In diagnostic applications, passive emissions and active sources in this frequency range are used to measure plasma parameters and dynamics; in particular, measurements of electron cyclotron emissions (ECEs) provide profile information regarding electron temperature. Recent developments in state-of-the-art 2D microwave imaging systems that measure fluctuations in electron temperature and density are largely based on ECE. The scattering process, phase delays, reflection/diffraction, and the polarization of actively launched EM waves provide us with the physics of magnetohydrodynamic instabilities and transport physics.