• 제목/요약/키워드: A/A Reactor System

검색결과 2,645건 처리시간 0.037초

혐기-호기 공정을 이용한 염료페수의 생물학적 처리 (Biological Treatemnt of Dye Wastewater Using an Anaerobic-Aerobic System)

  • 박영식;문정현;안갑환
    • 한국환경과학회지
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    • 제11권6호
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    • pp.569-576
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    • 2002
  • Anaerobic/aerobic reactor system was used to treat a synthetic wastewater with glucose as carbon sources(0.38~2.29 kg COD/m3.day) and Acid Red 14(1.05 "24.00 g Acid Red 141m3.day, color degree of 570 ~ 1710). COD removal efficiency by the anaerobic stage in operation period were above 90 % organic loading rate of 0.38 ~ 2.29 kg COD/m3.day(except, adaptation period) and the removal efficiency of the whole system were above 96 %. The decolorization of the Acid Red 14 was through the alteration of the dye structure(or cleavage of the Azo bond) during the anaerobic treatment. In the A/A system, the anaerobic stage played an essential role in removing both color and COD. In addition it also improves biodegradability of dye f3r further aerobic treatment. After operation, average MLSS concentration of anaerobic sludge reactor, anaerobic fixed-bed reactor and aerobic fixed-bed reactor were 17100mg/L, 20000mg/L, and 10000mg/L, respectively.

On the cyclic change in the dynamics of the IBR-2M pulsed reactor

  • Yu.N. Pepelyshev;Sumkhuu Davaasuren
    • Nuclear Engineering and Technology
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    • 제55권5호
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    • pp.1665-1670
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    • 2023
  • It is shown that in the IBR-2M reactor by the end of the reactor cycle, changes in dynamics are observed associated with a strong weakening of the fast power feedback (PF), as a result of which the reactor becomes oscillatorily unstable. After each week of zero-power operation the negative changes in reactor dynamics disappear and the stability of the reactor is restored. Thus, the reactor undergoes cyclic changes in the oscillatory instability. The correlation between of a fast PF and a slow PF is experimentally observed, which makes it possible to almost completely eliminate the cyclic component of instability by changing the control mode of rods of the control system.

$Hg_{1-x}Cd_xTe$ OMVPE System 과 ARIIV Reactor Chamber의 설계 및 제작 (Disign of $Hg_{1-x}Cd_xTe$ OMVPE System and ARIIV Reactor Chamber)

  • 한석룡
    • 한국진공학회지
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    • 제2권4호
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    • pp.410-415
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    • 1993
  • The direct growth OMVPE system, designed specificallyfor direct growth of Hg1-xCdxTe using annular rectant inlet inverted verticla (ARIIV) reactor, was constructed. This paper presents the detailed technical approach on a newly designed ARIIV reactor that increases Hg incorporation, imposes uniformity, and avoids the needs for temperature processing to create alloys by inter diffusion approach.

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ASSESSMENT OF A NEW DESIGN FOR A REACTOR CAVITY COOLING SYSTEM IN A VERY HIGH TEMPERATURE GAS-COOLED REACTOR

  • PARK GOON-CHERL;CHO YUN-JE;CHO HYOUNGKYU
    • Nuclear Engineering and Technology
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    • 제38권1호
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    • pp.45-60
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    • 2006
  • Presently, the VHTGR (Very High Temperature Gas-cooled Reactor) is considered the most attractive candidate for a GEN-IV reactor to produce hydrogen, which will be a key resource for future energy production. A new concept for a reactor cavity cooling system (RCCS), a critical safety feature in the VHTGR, is proposed in the present study. The proposed RCCS consists of passive water pool and active air cooling systems. These are employed to overcome the poor cooling capability of the air-cooled RCCS and the complex cavity structures of the water-cooled RCCS. In order to estimate the licensibility of the proposed design, its performance and integrity were tested experimentally with a reduced-scale mock-up facility, as well as with a separate-effect test facility (SET) for the 1/4 water pool of the RCCS-SNU to examine the heat transfer and pressure drop and code capability. This paper presents the test results for SET and validation of MARS-GCR, a system code for the safety analysis of a HTGR. In addition, CFX5.7, a computational fluid dynamics code, was also used for the code-to-code benchmark of MARS-GCR. From the present experimental and numerical studies, the efficacy of MARS-GCR in application to determining the optimal design of complicated systems such as a RCCS and evaluation of their feasibility has been validated.

Potentiometric Determination of L-Malate Using Ion-Selective Electrode in Flow Injection Analysis Syste

  • Kwun, In-Sook;Lee, Hye-Sung;Kim, Meera
    • Preventive Nutrition and Food Science
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    • 제4권1호
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    • pp.79-83
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    • 1999
  • A potentiometric biosensor employing a CO3-2 ion-selective electrode(ISE) and malic enzyme immobilization in al flow injection analysis (FIA) system was constructed. Analytical parameters were optimized for L-malate determination . The CO3-2 -ISE-FIA system was composed of a pump, an injector, a malic enzyme (EC1.1.1.40) reactor, a CO3-2 ion-selective electrode, a pH/mV meter and a recorder. Cofactor NADP was also injected with substrate for theenzyme reaction into the system. Optimized analytical parameters for L-malate determination in the CO3-2 ISE-FIA system were as follows ; flow rate, 14.5ml/hr ; sample injection volume, 100ul; enzyme loading in the reactor, 20 units ; length of the enzyme reactor , 7 cm ; tubing length form the enzyme reactor to the detector as a geometric factor in FIA, 15 cm . The response time for measuring the entire L-malate concentration range (10-2 ~10-5 mol/L ; 4 injections )was <15minutes . In this CO3-2 -ISE-FIA system, the potential differences due to th eformation of CO3-2 by the reaction of malic enzyme on L-malate were correlated to L-malate concentration in the range of 10-2 ~10-5mol/L ; the detection limit was 10-5 mol/L. This potentionmetric CO3-2 ISE--FIA system was found to be useful for L-malate measurement.

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원자로의 직접 디지탈 제어를 위한 최적 제어계통의 설계 (Design of optimal control system of nuclear reactor for direct digital control)

  • 천희영;박귀태;이기상
    • 전기의세계
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    • 제30권8호
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    • pp.509-516
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    • 1981
  • The optimal control theory is applied to the design of a digital control system for a nuclear reactor. A linear dynamic model obtained at 85% of rated power and a quadratic performance index are used. A minimal order observer used in cascade with the feedback controller is suggested as a state estimator. The total reactor power control is studied in the range of 80% to 100% of rated power, with the steady state and load-following control. The control algorithm considered is suitable for implementation in direct digital control.

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Conceptual design for a 5 kWe space nuclear reactor power system

  • Huaping Mei;Dali Yu;Shengqin Ma;Jiansong Zhang;Yongju Sun;Chao Chen;Meisheng He;Haixia Wang;Yang Li;Liang Wang;Taosheng Li;Jie Yu
    • Nuclear Engineering and Technology
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    • 제56권9호
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    • pp.3644-3653
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    • 2024
  • Enhancing the capabilities of unmanned space exploration, such as satellite monitoring and space science missions, requires efficient and reliable nuclear power systems. A viable solution is found in the 1-10 kWe power level of space nuclear reactor power systems, offering advantages such as a manageable research and development process, and relatively low investment requirements. This paper introduces a conceptual design for a 5 kWe space nuclear reactor power system, outlining its components and characteristics. The study includes a thorough analysis of potential challenges, encompassing heat pipe failure accidents, re-entry scenarios, and weight estimation considerations. The results demonstrate that the proposed space nuclear reactor power system effectively meets the safety requirements. The total mass of the power system is estimated at approximately 1.5 tons, with a specific mass of around 300 kg/kWe. This research contributes valuable insights for the design of space nuclear reactor power systems operating within a similar power range.

중성자 신호이용 원자로 내부 구조물 감시시스템 설계 (Design of Diagnostic System for Reactor Internal Structures Using Neutron Noise)

  • 박종범;박진호;황충완;김인국
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2000년도 추계학술대회 논문집 학회본부 D
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    • pp.638-640
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    • 2000
  • Reactor Noise is defined as the fluctuations of measured instrumentation signals during full-power operation of reactor which have informations on reactor system dynamics such as neutron kinetics, thermal-hydraulics, and structural dynamics. Reactor noise analyses of ex-core neutron detector internals such as fuel assembly and Core Support Barrel in Nuclear Power Plant. A real time mode separation technique have been developed and applied for the analyses. The analyses data base have been constructed for the continuous monitoring and diagnose of the reactor internals. Detailed design of diagnostic system reactor internal structures using neutron noise(RIDS).

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소듐냉각고속로 KALIMER-600 축소 물모의 열유동 가시화 실험장치 구축 및 거시 유동장 특성 측정 (Water-Simulant Facility Installation for the Sodium-Cooled Fast Reactor KALIMER-600 and Global Flow Measurement)

  • 차재은;김성오
    • 한국가시화정보학회지
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    • 제9권4호
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    • pp.54-62
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    • 2011
  • KAERI has developed a KALIMER-600 which is a pool-type sodium-cooled fast reactor with a 600MWe electric generation capacity. For a SFR development, one of the main topics is an enhancement of the reactor system safety. Therefore, we have a long-term plan to design the large sodium experimental facility to evaluate the reactor safety and component performance. In order to extrapolate a thermal hydraulic phenomena in a large sodium reactor, the thermal hydraulics phenomena is under investigation in a 1/$10^{th}$ water-simulant facility for the KALIMER-600. In this paper, we shortly described the experimental facility setup and the measurement of the isothermal global flow behavior. For the flow field measurement, the PIV method was used in a transparent Plexiglas reactor vessel model at around $20^{\circ}C$ water condition.

메탄발효를 위한 도시쓰레기 초고온 가용화 방법의 효율성 검토 (A Study of Biological Hydrolysis Efficiency for Methane Digestion with Municipal Solid Waste)

  • 천지훈
    • 상하수도학회지
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    • 제24권5호
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    • pp.561-572
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    • 2010
  • The efficiency of biological hydrolysis at $80^{\circ}C$ on municipal solid waste mixed with anaerobic digestion sludge was investigated in 100L batch reactors. The hydrolysis effect was observed within a day, when the hydrolysis reactor used for a pre-treatment reactor for methanogenesis, and the effect was observed during two days, When the reactor used for post-treatment reactor. For both configurations, methane production rate decreased, when hydrolysis was carried out more than a day. Gaseous ammonia in the hydrolysis reactors was successtully removed by the ammonia stripping system. Microbial diversity analysis on the hydrolysis reactors indicated dependency of microbial diversity on the configuration of the hydrolysis reactors. Carbohydrate and lactate degrading microbes dominated in the hydrolysis reactor, when the hydrolysis reactor used for a pre-treatment reactor for methanogenesis, while protein degrading microbes dominated in the post-treatment reactor.