• 제목/요약/키워드: (Advanced Power Plant Engineering & Simulation System)

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Study on The Development of Basic Simulation Network for Operational Transient Analysis of The CANDU Power Plant

  • Park, Jong-Woon;Lim, Jae-cheon;Suh, Jae-seung;Chung, Ji-bum;Kim, Sung-Bae
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1995년도 추계학술발표회논문집(1)
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    • pp.423-428
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    • 1995
  • Simulation models have been developed to predict the overall behavior of the CANDU plant systems during normal operational transients. For real time simulation purpose, simplified thermal hydraulic models are applied with appropriate system control logics, which include primary heat transport system solver with its component models and secondary side system models. The secondary side models are mainly used to provide boundary conditions for primary system calculation and to accomodate plant power control logics. Also, for the effective use of simulation package, hardware oriented basic simulation network has been established with appropriate graphic display system. Through validation with typical plant power maneuvering cases using proven plant performance analysis computer code, the present simulation package shows reasonable capability in the prediction of the dynamic behavior of plant variables during operational transients of CANDU plant, which means that this simulation tool can be utilized as a basic framework for full scope simulation network through further improvements.

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플랜트 동특성 해석용 소프트웨어 개발 및 초임계압 관류형 보일러에의 적용 (Development of Dynamic Simulation Software for Power Plant and its Application to Once-Through Boiler)

  • 이기현;이동수;조창호
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2000년도 추계학술대회논문집B
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    • pp.656-661
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    • 2000
  • In the recent trend of electric power supply market, a variable pressure operation supercritical once-through steam generator is highlighted as a thermal power plant for cycling load because of its superiority in load regulation. Almost all thermal power plants of the future are expected to be variable pressure operation supercritical once-through units. APESS(Advanced Plant Engineering & Simulation System) is a dynamic simulation software for power plant which is under being developed by Korea Heavy Industries & Construction Co., Ltd. This paper present the introduction of APESS and the result of simulation for variable pressure operation supercritical once-through steam generator.

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원도즈 NT/2000에서의 발전플랜트 동특성 해석시스템 그래픽 사용자 인터페이스 구현 (A GUI Implementation of a Power Plant Dynamic Simulation System on Windows NT/2000)

  • 이동수;이기현;조창호
    • 한국시뮬레이션학회:학술대회논문집
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    • 한국시뮬레이션학회 2002년도 춘계학술대회논문집
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    • pp.197-201
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    • 2002
  • APESS(Advanved Plant Engineering & Simulation System) is a dynamic simulation software for power plant which is being developed by Doosan Heavy Industries & Construction Co., Ltd. This Paper represents the GUI implementation of APESS on Windows NT/2000 operating system.

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Simulation of Reactor and Turbine Poler Transients in CANDU 6 Nuclear Power Plants

  • Park, Jong-Woon-;Yeom, Choong-Sub;Kim, Sung-Bae-
    • 한국에너지공학회:학술대회논문집
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    • 한국에너지공학회 1994년도 춘계학술발표회 초록집
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    • pp.130-137
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    • 1994
  • As a part of developing engineering simulator for CANDU 6 nuclear power plants, present paper gives the tentative simulation results of reactor and turbine power transients including reactor-follow-turbine operation. One point kinetics equations are used for neutron dynamics, iodine and xenon loads. To calculate time-dependent high and low pressure turbine powers and grid frequency deviation, simple first order differential equations are used. In addition, control logics (reactor regulating system, demand power routine, and unit power regulator) used in the plant's process computers have been referenced.

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Operation optimization of auxiliary electric boiler system in HTR-PM nuclear power plant

  • Du, Xingxuan;Ma, Xiaolong;Liu, Junfeng;Wu, Shifa;Wang, Pengfei
    • Nuclear Engineering and Technology
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    • 제54권8호
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    • pp.2840-2851
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    • 2022
  • Electric boilers (EBs) are the backup steam source for the auxiliary steam system of high-temperature gas-cooled reactor nuclear power plants. When the plant is in normal operations, the EB is always in hot standby status. However, the current hot standby operation strategy has problems of slow response, high power consumption, and long operation time. To solve these problems, this study focuses on the optimization of hot standby operations for the EB system. First, mathematical models of an electrode immersion EB and its accompanying deaerator were established. Then, a control simulation platform of the EB system was developed in MATLAB/Simulink implementing the established mathematical models and corresponding control systems. Finally, two optimization strategies for the EB hot standby operation were proposed, followed by dynamic simulations of the EB system transient from hot standby to normal operations. The results indicate that the proposed optimization strategies can significantly speed up the transient response of the EB system from hot standby to normal operations and reduce the power consumption in hot standby operations, improving the dynamic performance and economy of the system.

폐열회수 보일러의 동특성 시뮬레이션 (Dynamic Simulation of Heat Recovery Steam Generator)

  • 이기현;이동수;조창호
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 추계학술대회논문집B
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    • pp.847-852
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    • 2001
  • A thorough understanding of the transient behavior during load following and start-up is essential in the design and operation of an heat recovery steam generator(HRSG). During this period of time, material that is exposed to high temperature and experiences a large temperature variation is subject to high thermal stress. APESS(Advanced Plant Engineering & Simulation System) is a dynamic simulation software for power plant which is under being developed by Doosan Heavy Industries & Construction Co., Ltd. This paper present the introduction of APESS and the result of simulation for an heat recovery steam generator.

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PWSCC and System Engineering Development of Internal Inspection and Maintenance Methodology for RCS

  • Abdallah, Khaled Atya Ahmed;Mesquita, Patricia Alves Franca de;Yusoff, Norashila;Nam, GungIhn;Jung, JaeCheon;Lee, YoungKwan
    • 시스템엔지니어링학술지
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    • 제12권1호
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    • pp.89-103
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    • 2016
  • Due to safety of the plant, it became very clear the importance of study occurrence reactor coolant system (RCS) issues specially the primary water stress corrosion cracking (PWSCC). The Systems Engineering (SE) approach is characterized by the application of a structured engineering methodology for the design of a complex system or component. Robotic devices have been used for internal inspection, maintenance and performing remote welding and inspection in high-radiation areas. In this paper, PWSCC overview and inlay and over lay welding methodology introduced, concept of robotic device that can be inserted into the piping via Steam Generator (SG) main way to access to primary piping of pressurized water reactor (PWR) is developed based on SE methodology. A 3D model of the inspection system was developed along with the APR1400 (Advanced Power Reactor)reactor coolant systems (RCS) and internals with virtual 3D simulation of the operation for visualization to prove the validity of the concept.

Application of Flow Network Models of SINDA/FLUIN $T^{TM}$ to a Nuclear Power Plant System Thermal Hydraulic Code

  • Chung, Ji-Bum;Park, Jong-Woon
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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    • pp.641-646
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    • 1998
  • In order to enhance the dynamic and interactive simulation capability of a system thermal hydraulic code for nuclear power plant, applicability of flow network models in SINDA/FLUIN $T^{™}$ has been tested by modeling feedwater system and coupling to DSNP which is one of a system thermal hydraulic simulation code for a pressurized heavy water reactor. The feedwater system is selected since it is one of the most important balance of plant systems with a potential to greatly affect the behavior of nuclear steam supply system. The flow network model of this feedwater system consists of condenser, condensate pumps, low and high pressure heaters, deaerator, feedwater pumps, and control valves. This complicated flow network is modeled and coupled to DSNP and it is tested for several normal and abnormal transient conditions such turbine load maneuvering, turbine trip, and loss of class IV power. The results show reasonable behavior of the coupled code and also gives a good dynamic and interactive simulation capabilities for the several mild transient conditions. It has been found that coupling system thermal hydraulic code with a flow network code is a proper way of upgrading simulation capability of DSNP to mature nuclear plant analyzer (NPA).

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데이터 기반 설계기법 도입에 따른 원전 건설관리체계 개선방향 고찰 (A Study on Improvement of Nuclear Power Plant Construction System According to Data-centric Design Technique Introduction in Korea)

  • 임병기;변수진
    • 에너지공학
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    • 제25권1호
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    • pp.108-112
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    • 2016
  • 본 연구에서는 국내 원전 산업의 데이터 기반 설계기법 전환을 위하여 관련 문헌을 조사하고 데이터 기반 설계기술에 대한 개념을 정립하였다. 또한 국내외 원전 산업 기술동향 분석을 통해 데이터 기반 설계통합시스템 Framework 개발 및 관련 주요기능을 도출하였다. 국내 원전 건설 시 최신 설계통합시스템 적용에 따라 이를 활용하는 제작사, 시공사 및 발주자의 업무수행 방식 또한 전면적인 전환을 위한 원전 건설단계별 업무프로세스 개선방향을 도출하였다. 이는 기자재 3D 모델 통합, 3D CAD 모델생성, 시공검토 Simulation 등 모델기반 현장설계 수행이 가능하며, 현장설계에서 발생하는 모든 설계도면 및 관련 정보가 데이터 기반 3D CAD 시스템으로 통합관리가 가능하여 이를 운영단계에 이관하여 O&M 단계에서 데이터 기반 운영체계가 가능함에 따라 발전소 안전 운영에 향상이 기대된다.

A Case Study on Designing a Console Design Review System Considering Operators' Viewing Range and Anthropometric Data

  • Cha, Woo Chang;Choi, Eun Gyeong
    • 대한인간공학회지
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    • 제36권5호
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    • pp.373-383
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    • 2017
  • Objective: The aim of this study is to introduce an operator console design review system suitable for designing and evaluating consoles based on human factor guidelines for a digitalized main control room in an advanced nuclear power plant which has a requirement for anthropometric data usage. Background: The system interface of the main control room in a nuclear power plant has been getting digitalized and consists of various consoles with many information displays. Console operators often face human-computer interactive problems due to inappropriate console design stemming from the perceptual constraints of anthropometric data usage. Method: Computational models with a process of visual perception and variables of anthropometric data are used for designing and evaluating operator consoles suitable for human system interface guidelines, which are used in an advanced nuclear power plant. Results: From the computational model and simulation application, console dimensions and a designing test module, which would be used for designing suitable consoles with safety concerns in a nuclear power plant, have been introduced. Conclusion: This case study may influence employing a suitable design concept with various anthropometric data in many areas with safety concerns and may show a feasible solution to designing and evaluating the safety console dimensions. Application: The results of this study may be used for designing a control room with the human factors requiring a safe working environment.