• Title/Summary/Keyword: STEAM capability

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RCGVS Design Improvement and Depressurization Capability Tests for Ulchin Nuclear Power Plant Units 3 and 4

  • Sung, Kang-Sik;Seong, Ho-Je;Jeong, Won-Sang;Seo, Jong-Tae;Lee, Sang-Keun;Keun hyo Lim;Park, Kwon-Sik;Oh, Chul-Sung
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.417-422
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    • 1998
  • he Reactor Coolant Gas Vent System(RCGVS) design for Ulchin Nuclear Power Plant Units 3&4(UCN 3&4) has been improved from the Yonggwang Nuclear Power Plant Units 3&4(YGN 3&4) based on the evaluation results for depressurization capability tests performed at YGN 3&4. There has been a series of plant safety analyses for Natural Circulation Cooldown(NCC) event and thermo-dynamic analyses with RELAP5 code for the steam blowdown Phenomena in order to optimize the orifice size of UCN 3&4 RCGVS. Baesd on these analyses results, the RCGVS orifice size for UCN 3&4 has been reduced to 9/32 inch from the l1/32 inch for YGN 3&4. The depressurization capability tests, which were performed at UCN 3 in order to verify the FSAR NCC analysis results, show that the RCGVS depressurization rates are being within the acceptable ranges. Therefore, it is concluded that the orificed flow path of UCN 3&4 RCGVS is adequately designed, and can provide the safety-grade depressurization capability required for a safe plant operation.

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Performance Analysis of a Triple Pressure HRSG

  • Shin, Jee-Young;Son, Young-Seok;Kim, Moo-Geun;Kim, Jae-Soo-;Jeon, Yong-Joon
    • Journal of Mechanical Science and Technology
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    • v.17 no.11
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    • pp.1746-1755
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    • 2003
  • Operating characteristics of a triple pressure reheat HRSG are analyzed using a commercial software package (Gate Cycle by GE Enter Software). The calculation routine determines all the design parameters including configuration and area of each heat exchanger. The off-design calculation part has the capability of simulating the effect of any operating parameters such as power load, process requirements, and operating mode, etc., on the transient performance of the plant. The arrangement of high-temperature and intermediate-temperature components of the HRSG is changed, and its effect on the steam turbine performance and HRSG characteristics is examined. It is shown that there could be a significant difference in HRSG sizes even though thermal performance is not in great deviation. From the viewpoint of both economics and steam turbine performance, it should be carefully reviewed whether the optimum design point could exist. Off-design performance could be one of the main factors in arranging components of the HRSG because power plants operate at various off-design conditions such as ambient temperature and gas turbine load, etc. It is shown that different heat exchanger configurations lead to different performances with ambient temperature, even though they have almost the same performances at design points.

A Feasibility Study on Geothermal Power Plant in Korea (한국형 지열발전 타당성 연구)

  • Lim, Hyo-Jae;Kwon, Jung-Tae;Kim, Geum-Soo;Chang, Ki-Chang
    • Proceedings of the SAREK Conference
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    • 2009.06a
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    • pp.39-44
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    • 2009
  • Geothermal energy is the heat contained in the earth and its internal fluids. Geothermal energy is stored as sensible or latent heat. Supplied by both internal and external sources, it represents a vast supply which is only started to be tapped for generation of electric power. In general, this is natural dry or wet medium to high enthalpy steam at temperatures above $150^{\circ}C$. For some time, binary systems employing substances with a lower boiling point than water in a secondary circuit have been used to generate vapor for driving turbines at a lower temperature level. The utilization of binary plants and the possibility of production from enhanced geothermal systems can expand its availability on a worldwide basis. The geothermal electricity installed capacity is approaching the 10,000GW threshold. Geothermal energy is not present everywhere, but its baseload capability is a very important factor for its success.

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SAFETY ANALYSIS OF INCREASE IN HEAT REMOVAL FROM REACTOR COOLANT SYSTEM WITH INADVERTENT OPERATION OF PASSIVE RESIDUAL HEAT REMOVAL AT NO-LOAD CONDITIONS

  • SHAO, GE;CAO, XUEWU
    • Nuclear Engineering and Technology
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    • v.47 no.4
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    • pp.434-442
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    • 2015
  • The advanced passive pressurized water reactor (PWR) is being constructed in China and the passive residual heat removal (PRHR) system was designed to remove the decay heat. During accident scenarios with increase of heat removal from the primary coolant system, the actuation of the PRHR will enhance the cooldown of the primary coolant system. There is a risk of power excursion during the cooldown of the primary coolant system. Therefore, it is necessary to analyze the thermal hydraulic behavior of the reactor coolant system (RCS) at this condition. The advanced passive PWR model, including major components in the RCS, is built by SCDAP/RELAP5 code. The thermal hydraulic behavior of the core is studied for two typical accident sequences with PRHR actuation to investigate the core cooling capability with conservative assumptions, a main steam line break (MSLB) event and inadvertent opening of a steam generator (SG) safety valve event. The results show that the core is ultimately shut down by the boric acid solution delivered by Core Makeup Tank (CMT) injections. The effects of CMT boric acid concentration and the activation delay time on accident consequences are analyzed for MSLB, which shows that there is no consequential damage to the fuel or reactor coolant system in the selected conditions.

An Experimental Study of Thermal Mixing of Steam Jet Condensation through an I-Sparser in a Quench Tank (수조내 I-Sparser의 증기제트 응축에 의한 열혼합 실험)

  • Kim Yeon-Sik;Jun Hyeong-Gil;Song Chul-Hwa
    • Journal of Energy Engineering
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    • v.14 no.1
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    • pp.62-71
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    • 2005
  • An experimental study on thermal mixing of steam jet condensation through the I-Sparger of APR1400 design using B&C (Blowdown and Condensation) test facility. Due to the limit of the steam supply capability of the pressurizer, transient thermal mixing experiments were conducted. Temperature distributions in the quench tank were measured using thermocouples located at various positions. From the experimental data, local temperature variations for various locations and vertically cross-sectional temperature distributions for several times were depicted and presented. The result shows the characteristics of thermal mixing of the I-Sparger depending on the design features of the I-Sparger.

Present Condition and View of Eddy Current Testing Probe for Nuclear Power Plant Steam Generator Tube Examination (원전 증기발생기 세관 검사를 위한 와전류 탐상 프로브의 현황 및 전망)

  • Kim Ji-Ho;Lee Hyang-Beom
    • 한국정보통신설비학회:학술대회논문집
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    • 2006.08a
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    • pp.241-245
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    • 2006
  • In the examination of Steam Generator (SG) tube in Nuclear Power Plant (NPP) Eddy Current Testing (ECT) probes play an Important role in detecting the defects. Bobbin probe and Rotating Pancake Coil (RPC) probe is usually used for the inspection of SG tube. Bobbin probe is good at high speed inspection, but ability of detection of circumferential defect is very weak. On the contrary RPC probe, which moves for inspection in the direction of axial and circumferential simultaneously, has very slow inspection speed, but it was excellent detection capability fur small cracks, which is hardly detected by bobbin probe. Many examinations of SG tube examination of NPP are achieved during short period. Therefore, solution about this must develop probe of new form for examination performance and examination time shortening of other probe. In this paper, analyzed technological present condition of Bob-bin probe and RPC probe been using in Nondestructive Testing (NDT) for SG tube defect detection and Appeared about background theory and view of developed probe newly.

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Thermal Flow Analysis of Operating Parameters in Autothermal Reformer (자열개질기의 운용조건에 따른 열유동 수치해석)

  • Park, Seung-Hwan;Kim, Jin-Wook;Park, Dal-Yung;Kim, Jae-Dong;Lee, Do-Hyung
    • The KSFM Journal of Fluid Machinery
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    • v.14 no.6
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    • pp.61-67
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    • 2011
  • The study is to analyze the chemical and heat-flow reactions in the hydrogen generation unit(autothermal reformer), using computational numerical tools. Autothermal reformer(ATR) is involved in complex chemical reaction, mass and heat transfer due to exothermic and endothermic reactions. Therefore it is necessary to reveal the effects of various operation parameters and geometries on the ATR performance by using numerical analysis. Numerical analysis needs to dominant chemical reactions that includes Full Combustion(FC) reaction, Steam Reforming(SR) reaction, Water-Gas Shift(WGS) reaction and Direct Steam Reforming(DSR) reaction. The objective of the study is to improve theoretically the reformer design capability for the goal of high hydrogen production in the autothermal reformer using methane. Hydrogen production reached maximum in a certain value of Oxygen to Carbon Ratio(OCR) or Steam to Carbon Ratio(SCR). When the longitudinal distance to dimeter ratio(L/D) is increased, hydrogen production increases.

Development of An Nuclear Steam Supply System Thermal-Hydraulic Program for the Westinghouse Type Nuclear Power Plant Simulator Using A Best-Estimate Code (최적 계통분석 코드를 이용한 웨스팅하우스형 원자력발전소 시뮬레이터용 핵 증기 공급 계통 열수력 프로그램 개발)

  • 서재승;전규동;이명수;이용관
    • Proceedings of the Korea Society for Simulation Conference
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    • 2004.05a
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    • pp.94-100
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    • 2004
  • KEPRI has developed an Nuclear Steam Supply System(NSSS) thermal-hydraulic simulation program (called ARTS-KORIl) based on the best-estimate system code, RETRAN, as a part of the development project for the KORI unit 1 nuclear power plant simulator. To develop the RETRAN code as an NSSS T/H engine for the simulator, a number of code modifications, such as simplifications and removing of discontinuities of the physical correlations, were made to satisfy the simulator requirements of robustness and real time calculation capability Some simplified models and a backup system were also developed to simulate some transients that cannot be efficiently calculated by the RETRAN part of ARTS-KORIl.

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Evaluation of the TEXAS-V Fragmentation Models Against Experimental Data

  • Song Jin H.;Park Ik K.;Nilsuwankosit Sunchai
    • Nuclear Engineering and Technology
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    • v.36 no.3
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    • pp.276-284
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    • 2004
  • This paper presents the results of the TEXAS-V computer code simulations of FARO L-14, L-28, and L-33. The old break-up model and new break-up model are tested to compare the respective simulations of each. As these experimental data sets cover a wide range of ambient pressures, sub-cooling of the water pool, and the melt jet diameters, the results of the simulations will be beneficial in assessing the TEXAS-V code's capability to predict the steam explosion phenomena in a prototypical reactor case. The current model was found to have some deficiencies, and the modules for the fragmentation, the equation of state, and the interfacial area for each flow regime in TEXAS-V were improved for the simulation of FARO L28 and FARO L-33.

STEAM Program Development for Career Exploration using VR Webtoon - Application of Contact·Untact Combined Education (VR 웹툰을 활용한 진로탐색형 STEAM 프로그램 개발 - 대면·비대면 혼합형 교육 적용 사례)

  • Joo, Hak-Jong;Lim, Eun-Young;Seo, Kyung-Min
    • Journal of The Korean Association of Information Education
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    • v.25 no.4
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    • pp.653-664
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    • 2021
  • This study proposes a STEAM (Science, Technology, Engineering, Arts, and Mathematics) program for career exploration of middle school students. The proposed program utilizes VR (Virtual Reality) for new digital technology and webtoon as a popular cultural element. It enables the students to investigate promising fields and experience them virtually for themselves. We design the program based on the 2015 revised curriculum, which enhances the learning effects with existing subjects. In particular, the program provides a hybrid education to combine contact and untact classes considering the COVID-19 situation. The educational goal of the proposed program is to improve creativity and convergence capability. Specifically, it aims to prepare an educational foundation that integrates new digital technologies into education and applies the programs to school education fields. To prove the effectiveness of the developed program, we applied the program to the second graders of A middle school located in Seoul. We expect that the proposed program helps students learn how to utilize new digital technologies and explore future career paths.