• Title/Summary/Keyword: steam injection

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Study on the cooling water supply method to the cooling water injection nozzle in the steam generator (증기발생기 내 냉각수 분사 노즐로의 냉각수 공급 방법에 관한 연구)

  • Oh, Jeong-hwa;Shin, Min-kyu;Cho, Young-seok;Ko, Young-sung
    • Journal of Aerospace System Engineering
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    • v.14 no.5
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    • pp.66-72
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    • 2020
  • In this study, a method for increasing the initial water supply was employed to protect the water injection nozzle by the flame when supplying the water to the steam generator. During the initial steam generator test, the flow rate was controlled by using the only venturi, but cooling water was not supplied to the combustion chamber at the beginning of combustion, thereby resulting in damage to the water nozzle. To solve this problem, a venturi and an orifice were configured in parallel to increase the initial supply flow rate to form a differential pressure between the water manifold and the combustion chamber. Venturi and orifice supply sequences were established through the water flow tests, and combustion tests were conducted for final verification. Consequently, a continuous supply of the cooling water at the beginning of combustion was achieved, and the experiment was successfully performed without damaging the cooling water nozzle.

Effect of Condensation on Spray Characteristics of Simplex Swirl Nozzle (응축이 심플렉스 와류 노즐의 분무 특성에 미치는 영향)

  • Koh, Kwang-Uoong;Lee, Sang-Yong
    • Proceedings of the KSME Conference
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    • 2001.06e
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    • pp.107-112
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    • 2001
  • The effect of ambient gas (steam) condensation on swirl spray characteristics were studied experimentally for low subcooling condition of the liquid. The configuration of the liquid(water) sheet and the breakup modes were examined. Also variation of the discharge coefficient, breakup length, local and the cross-sectional area-averaged SMD of droplets with the liquid flow(injection) rate were obtained. The perforation breakup mode appears dominant with condensation while the aerodynamic wave breakup mode is dominant without condensation(in the air environment). The discharge coefficient, breakup length and the mean drop sizes decrease in a same manner with increasing of the liquid flow rate for both cases(with and without condensation). The condensation effects are insignificant with the discharge coefficient. However, the local and cross-sectional area-averaged SMD are larger and the breakup length becomes shorter in the steam environment. The spray angle predicted from the volumetric flux distribution along the radial direction of the sprays in the steam environment becomes larger with condensation.

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Analysis of Transient Characteristics of a Steam Power Plant System (증기발전 시스템의 과도상태 특성 해석)

  • Park, Keun-Han;Kim, Tong-Seop;Ro, Sung-Tack
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.24 no.7
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    • pp.967-975
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    • 2000
  • Transient characteristics of a boiler and turbine system for a steam power plant are simulated. One-dimensional unsteady models are introduced for each component. An interaction between boiler and turbine and a control of the water level in the drum are taken into account. Transient responses of the system to the variations of main system variables such as fuel and air flow rate, cooling water injection rate at the attemperator, gas recirculation rate at the furnace and opening of the turbine control valve are examined. Effect of fluid inertia and tube wall thermal inertia on predicted dynamic behavior is investigated.

A Study on Effect of Urea-SCR Aftertreatment System upon Exhaust Emissions in a LPG Steam Boiler (LPG 증기보일러의 배기 배출물에 미치는 요소-SCR 후처리 시스템의 영향에 관한 연구)

  • Bae, Myung-Whan;Song, Byung-Ho
    • Transactions of the Korean Society of Automotive Engineers
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    • v.22 no.3
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    • pp.1-11
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    • 2014
  • The aim of this study is to investigate the effect of SCR reactor on the exhaust emissions characteristics in order to develop a urea-SCR aftertreatment system for reducing $NO_x$ emissions. The experiments are conducted by using a flue tube LPG steam boiler with the urea-SCR aftertreatment system. The urea-SCR aftertreatment system utilizes the ammonia converted from 17% aqueous urea solution injected in front of SCR catalyst as a reducing agent for reducing $NO_x$ emissions. The equivalence ratio, urea injection amount, ammonia slip and $NO_x$ conversion efficiency relative to boiler load are applied to discuss the experimental results. In this experiment, the average equivalence ratio is calculated by changing only the fuel consumption rate while the intake air amount is constantly fixed at $25,957.11cm^3/sec$. The average equivalence ratios are 1.38, 1.11, 0.81 and 0.57 when boiler loads are 100, 80, 60 and 40%. The $NO_x$ conversion efficiency is raised with increasing urea injection amount, and $NH_3$ slip is also boosted at the same time. Consequently, the $NO_x$ conversion efficiency relative to boiler load should be examined in combination with urea injection amount and $NH_3$ slip. The results are calculated by 89, 85, 77 and 79% for the boiler loads of 100, 80, 60 and 40%. The appropriate amount of urea injection for the respective boiler load can be not discussed by only $NO_x$ emissions, and should be determined by considering the $NO_x$ conversion efficiency, $NH_3$ slip and reactive activation temperature simultaneously. In this study, the urea amounts of 230, 235, 233 and 231 mg/min are injected at the boiler loads of 100, 80, 60 and 40%, and the final $NH_3$ slips are measured by 8.48, 5.58, 11.97 and 11.34 ppm at the same conditions. THC emission is affected by the SCR reactor under other experimental conditions except 100% engine load, and CO emission at only 40% engine load. The rest of exhaust emissions are not affected by the SCR reactor under all experimental conditions.

EVALUATION OF AN ACCIDENT MANAGEMENT STRATEGY OF EMERGENCY WATER INJECTION USING FIRE ENGINES IN A TYPICAL PRESSURIZED WATER REACTOR

  • PARK, SOO-YONG;AHN, KWANG-IL
    • Nuclear Engineering and Technology
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    • v.47 no.6
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    • pp.719-728
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    • 2015
  • Following the Fukushima accident, a special safety inspection was conducted in Korea. The inspection results show that Korean nuclear power plants have no imminent risk for expected maximum potential earthquake or coastal flooding. However long- and short-term safety improvements do need to be implemented. One of the measures to increase the mitigation capability during a prolonged station blackout (SBO) accident is installing injection flow paths to provide emergency cooling water of external sources using fire engines to the steam generators or reactor cooling systems. This paper illustrates an evaluation of the effectiveness of external cooling water injection strategies using fire trucks during a potential extended SBO accident in a 1,000 MWe pressurized water reactor. With regard to the effectiveness of external cooling water injection strategies using fire engines, the strategies are judged to be very feasible for a long-term SBO, but are not likely to be effective for a short-term SBO.

The study on the variable orifice spray of the steam power plant desuperheater (화력발전설비의 과열증기저감용 가변오리피스 분사 특성)

  • Kim, Jeong-Sik;Kim, Kwang-Hee;Lee, Jong-Sun
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.14 no.1
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    • pp.63-68
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    • 2013
  • The steam power plant is becoming more important to supply a stable power lately. Desuperheater of the steam power plant facility plays a role in maintaining the proper superheat to avoid damage turbine power due to the superheated steam produced in the boiler. In this study, when the steam flows $530^{\circ}C$, 36.7 kg/s, 1.36 MPa in the 460mm pipe, variable orifice nozzle developed in Korea was carried out the performance analysis in coolant injection conditions of $150^{\circ}C$, 4.28 MPa. Findings, steam pipe coolant temperature was maintained at $446^{\circ}C$ and sprayed droplet size was verified by $50{\mu}m$ or less.

Phenomena Identification and Ranking Table for the APR-1400 Main Steam Line Break

  • Song, J.H.;Chung, B.D.;Jeong, J.J.;Baek, W.P.;Lee, S.Y.;Choi, C.J.;Lee, C.S.;Lee, S.J.;Um, K.S.;Kim, H.G.;Bang, Y.S.
    • Nuclear Engineering and Technology
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    • v.36 no.5
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    • pp.388-402
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    • 2004
  • A phenomena identification and ranking table(PIRT) was developed for a main steam line break (MSLB) event for the Advanced Power Reactor-1400 (APR-1400). The selectee event was a double-ended steam line break at full power, with the reactor coolant pump running. The developmental panel selected the fuel performance as the primary safety criterion during the ranking process. The plant design data, the results of the APR-1400 safety analysis, and the results of an additional best-estimate analysis by the MARS computer code were used in the development of the PIRT. The period of the transient was composed of three phases: pre-trip, rapid cool-down, and safety injection. Based on the relative importance to the primary evaluation criterion, the ranking of each system, component, and phenomenon/process was performed for each time phase. Finally, the knowledge-level for each important process for certain components was ranked in terms of existing knowledge. The PIRT can be used as a guide for planning cost-effective experimental programs and for code development efforts, especially for the quantification of those processes and/or phenomena that are highly important, but not well understood.

Effect of CO2 Injection in SAGD Process for Oil Sand Bitumen Recovery (고온 고압 스팀을 주입하는 SAGD 공정에서 CO2주입이 오일샌드 역청 회수율에 미치는 영향)

  • Song, Byung Jin;You, Nansuk;Lee, Jae Hoon;Lee, Chul Wee
    • Applied Chemistry for Engineering
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    • v.25 no.3
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    • pp.262-267
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    • 2014
  • SAGD (steam assisted gravity drainage) process is the most commonly used in-situ technology for the recovery of bitumen from oil sand. It was investigated that the effects of different additives on bitumen recovery rate from oil sand in SAGD process among many possible mechanisms studied throughout the study. Bitumen recovery from thin layer oil sand reservoirs was simulated by using an experimental SAGD apparatus with scale of 150:1. To improve the simulation accuracy of thin layer oil reservoir, we have attached geological model (GM). Oil sand was simulated by using a mixture of extra heavy oil and glass beads with a diameter of 1.5 mm. $CO_2$ was used as an additive and the evolution of steam chambers were closely monitored, and the effects of $CO_2$ as an additive was investigated. Two types of injection methods were tested; continuous ($cCO_2$-SAGD) and sequential interruption ($sCO_2$-SAGD) $CO_2$ injection. For the $sCO_2$-SAGD experiment, it was observed that the recovery rates and CSOR were efficiently improved control experiment from 60.2% to 69.3% and 7.1 to 6.0, respectively, whereas $cCO_2$-SAGD experiment decreased from 60.2% to 57.6% and 7.1 to 7.3.

A Study for Optimal Design of the AIG to Improve the Performance of DeNOx Facilities Installed in Combined Cycle Plant (복합화력 탈질설비 성능향상을 위한 암모니아 주입 그리드의 최적설계 방안에 관한 연구)

  • Kim, Kwang-Chu;Park, Man-Heung;Yoon, Jun-Kyu;Lim, Jong-Han
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.19 no.12
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    • pp.811-820
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    • 2007
  • A Study on the optimal design of the AIG(Ammonia Injection Grid) to improve the performance of DeNOx facilities in the HRSG(Heat Recovery Steam Generator) was performed using the CFD analysis. On the basis of the flow analysis results in the case that the AIG in the HRSG was not installed, the numerical analyses according to the positions of AIG, injection angles of nozzle and the control of ammonia injection quantity were carried out. The standard deviation according to factors was calculated for quantitative comparison. As the results, the AIG in the HRSG should be installed in the position that the uniform flow field shows through the exact flow analysis in the previous of the AIG design and installation. In the case the AIG has already been installed and non uniform flow distribution shows, it is recommended that flow correction device or KoNOx catalyst should be used. Otherwise, the control of ammonia injection angle or the ammonia injection quantity using the velocity profile analysis is demanded to accomplish the optimal performance.

Direct ECC Bypass Phenomena in the MIDAS Test Facility During LBLOCA Reflood Phase

  • B.J. Yun;T.S. Kwon;D.J. Euh;I.C. Chu;Park, W.M.;C.H. Song;Park, J.K.
    • Nuclear Engineering and Technology
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    • v.34 no.5
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    • pp.421-432
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    • 2002
  • As one of the advanced design features of the APR1400, direct vessel injection (DVI) system is being considered instead of conventional cold leg injection (CLI) system. It is known that the DVI system greatly enhances the reliability of the emergency core cooling (ECC) system. However, there is still a dispute on its performance in terms of water delivery to the reactor core during the reflood phase of a large-break loss-of-coolant accident (LOCA). Thus, experimental validation is under progress. In this paper, test results of direct ECC bypass performed in the steam-water test facility tailed MIDAS (Multi-dimensional Investigation in Downcomer Annulus Simulation) are presented. The test condition is determined, based on the preliminary analysis of TRAC code, by applying the ‘modified linear scaling method’with the l/4.93 length scale . From the tests, ECC direct bypass fraction, steam condensation rate and information on the flow distribution in the upper annulus downcomer region are obtained.