• Title/Summary/Keyword: Coolant Control

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Flow Characteristics Evaluation in Reactor Coolant System for Full System Decontamination of Kori-1 Nuclear Power Plant (고리1호기 계통제염을 위한 원자로냉각재내 유동 특성 평가)

  • Kim, Hak Soo;Kim, Cho-Rong
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.16 no.3
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    • pp.389-396
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    • 2018
  • The Kori-1 Nuclear Power Plant (NPP), WH 2-Loop Pressurized Water Reactor (PWR) operated for approximately 40 years in Korea, was permanently ceased on June 18, 2017. To reduce worker exposure to radiation by reducing the dose rate in the system before starting main decommissioning activities, the permanently ceased Kori-1 NPP will be subjected to full system decontamination. Generally, the range of system decontamination includes Reactor Pressure Vessels (RPV), Pressurizer (PZR), Steam Generators (SG), Chemical & Volume Control System (CVCS), Residual Heat Removal System (RHRS), and Reactor Coolant System (RCS) piping. In order to decontaminate these systems and equipment in an effective manner, it is necessary to evaluate the influence of the flow characteristics in the RCS during the decontamination period. There are various methods of providing circulating flow rate to the system decontamination. In this paper, the flow characteristics in Kori-1 NPP reactor coolant according to RHR pump operation were evaluated. The evaluation results showed that system decontamination using an RHR pump was not effective at decontamination due first to impurities deposited in piping and equipment, and second to the extreme flow unbalance in the RCS caused deposition of impurities.

Dynamic Characteristics on the CRDM of SMART Reactor (SMART 원자로 제어봉 구동 장치의 동특성해석)

  • Lee, Jang-Won;Cho, Sang-Soon;Kim, Dong-Ok;Park, Jin-Seok;Lee, Won-Jae
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.34 no.8
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    • pp.1105-1111
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    • 2010
  • The Korea Atomic Energy Research Institutes has been developing the SMART (System integrated Modular Advanced ReacTor), an environment-friendly nuclear reactor for the generation of electricity and to perform desalination. SMART reactors can be exposed to various external and internal loads caused by seismic and coolant flows. The CRDM(control rod drive mechanism), one of structures of the SMART, is a component which is adjusting inserting amount of a control rod, controlling output of reactor power and in an emergency situation, inserting a control rod to stop the reactor. The purpose of this research is performing the analysis of dynamic characteristic to ensure safety and integrity of structure of CRDM. This paper presents two FE-models, 3-D solid model and simplified Beam model of the CRDM in the coolant, and then compared the results of the dynamic characteristic about the two FE-models using a commercial Finite Element tool, ABAQUS CAE V6.8 and ANSYS V12. Beam 4 and beam 188 of simplified-model were also compared each other. And simplified model is updated for accuracy compare to 3-D solid.

Implementation of EPICS based control system for KSTAR Current Lead System (KSTAR 전류전송제어시스템의 원격운전을 위한 EPICS 기반 제어계 구축)

  • Kim, Myung-Kyu;Baek, S.H.;Kim, K.H.;Park, M.K.
    • Journal of the Korean Vacuum Society
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    • v.17 no.1
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    • pp.58-66
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    • 2008
  • The KSTAR Current Lead System(CLS) with network based real-time distributed control system is implemented using an EPICS as a middle-ware software. The current lead system transfers current from magnet power supplies to superconducting magnet system and simultaneously supply the coolant to maintain superconducting state. To control the CLS at main control room an EPICS IOC server is installed in local control area. Using this server, it is able to be controlled and monitored the system in main control room through operator interface(OPI) which uses "caget" to read status and "caput" to write command with a unique name called PV. The EPICS IOC is developed using "ether-ip" driver to communicate with PLC. Also we achieved satisfactory results in operation and stability aspects from a long period commissioning test.

Study on the cooling control algorithm of electronic devices for an electric vehicle: Part 1 Effectiveness analysis of general control logic (전기자동차용 전자장비 냉각 제어 알고리즘에 관한 연구: Part 1 일반 냉각 제어 로직 유효성 분석)

  • Seo, Jae-Hyeong;Kim, Dae-Wan;Chung, Tae-Young;Jung, Tae-Hee;Lee, Moo-Yeon
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.15 no.4
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    • pp.1850-1858
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    • 2014
  • The object of this study is to develop an cooling control algorithm for electronics devices of the electric vehicle. In order to estimate the existing cooling control logic of the electronic devices for the small and medium sized electric vehicle, the experiments on the coolant temperature variation of the cooling system were conducted under 4 different seasons conditions. As a result, the existing cooling control logic were overcooled when it was compared with the reference temperature for a required cooling load. In addition, the newly developed optimum cooling control logic for improving the mileages of the tested electric vehicle with consideration of the ambient temperature, vehicle speed, and refrigerant temperature of the air conditioning on/off is necessary.

Robust power control design for a small pressurized water reactor using an H infinity mixed sensitivity method

  • Yan, Xu;Wang, Pengfei;Qing, Junyan;Wu, Shifa;Zhao, Fuyu
    • Nuclear Engineering and Technology
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    • v.52 no.7
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    • pp.1443-1451
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    • 2020
  • The objective of this study is to design a robust power control system for a small pressurized water reactor (PWR) to achieve stable power operations under conditions of external disturbances and internal model uncertainties. For this purpose, the multiple-input multiple-output transfer function models of the reactor core at five power levels are derived from point reactor kinetics equations and the Mann's thermodynamic model. Using the transfer function models, five local reactor power controllers are designed using an H infinity (H) mixed sensitivity method to minimize the core power disturbance under various uncertainties at the five power levels, respectively. Then a multimodel approach with triangular membership functions is employed to integrate the five local controllers into a multimodel robust control system that is applicable for the entire power range. The performance of the robust power system is assessed against 10% of full power (FP) step load increase transients with coolant inlet temperature disturbances at different power levels and large-scope, rapid ramp load change transient. The simulation results show that the robust control system could maintain satisfactory control performance and good robustness of the reactor under external disturbances and internal model uncertainties, demonstrating the effective of the robust power control design.

Development of Rapid Cooling System for Injection Mold (사출금형의 급속냉각시스템 개발)

  • Moon, Young-Bae;Choi, Youn-Sik;Jeong, Yeong-Deug
    • Design & Manufacturing
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    • v.8 no.1
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    • pp.31-34
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    • 2014
  • The Injection molding is used more than 70% of total production in plastic products. The injection molding process has 4 processes such as filling, packing, cooling and ejecting. It spends most of times in the cooling process. Therefore, it is important to control the mold temperature in producing plastic products. The cooling system and time affect the product's quality and productivity. Especially, cooling time has about 60% of total injection cycle time. Therefore, we can improve a productivity by shortening cooling time. In this study, the rapid cooling system was developed and performed a efficiency test. This system could refrigerate coolant to $1^{\circ}C$ and had to need 10 minutes for normal operating. However, if response time of temperature controller and sensor will be increased, the performance of this system will increase.

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Modelling of Thermal Discharge Performance for Ice-on-coil Type Ice-Storage Tank (관외착빙형 빙축열조의 방열성능 모델링)

  • Lee, Sang-Ryoul;Lee, Kyoung-Ho;Choi, Byoung-Youn;Han, Seong-Ho
    • Proceedings of the KSME Conference
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    • 2001.06d
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    • pp.280-285
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    • 2001
  • This paper presents a modelling of thermal discharge performance for a static ice-on-coil ice-storage tank. Through the present study, discharging characteristics were examined with the existing results of theoretical and numerical heat transfer analyses. Also, an experiment was conducted to obtain a real set of discharge performance. The thermal effectiveness, the ratio of the actual heat transfer rate to the maximum possible heat transfer rate, decreased when the stored energy decreased during discharging period. And the effectiveness increased as the coolant flow rate through the storage increased, of which increasing rate decreased abruptly near the maximum and the minimum stored energy. An empirical correlation was obtained from the experimental and the numerical analysis data.

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Development of Rapid Cooling System using Peltier Device (펠티에 소자를 이용한 급속 냉각시스템의 개발)

  • Jang, M.K.;Lee, G.H.;Noh, K.C.;Jeong, Y.D.
    • Journal of Power System Engineering
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    • v.13 no.4
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    • pp.38-42
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    • 2009
  • The Injection molding is used more than 70% of total production in plastic products. The injection molding process has 4 processes such as filling, packing, cooling and ejecting. now then, cooling process spends the most of times in Injection molding cycle time. Therefore, it is important to control the mold temperature in producing plastic products. The cooling system and time affect the product's quality and productivity. Especially, cooling time has about 60% of total injection cycle time. Therefore, we can improve a productivity by shortening cooling time. In this study, the rapid cooling system was developed and performed a efficiency test. This system could refrigerate coolant to $1^{\circ}C$ and had to need 10 minutes for normal operating.

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The HPRF system for PEFP 20MeV proton linac

  • Seol, K.T.;Kwon, H.J.;Song, Y.G.;Park, M.Y.;Cho, Y.S.
    • Proceedings of the Korean Nuclear Society Conference
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    • 2004.10a
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    • pp.683-684
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    • 2004
  • The RF system for PEFP 20MeV proton linear accelerator is described. The RF system for 3MeV RFQ was already installed and operated to drive the RFQ. The klystron was tested up to 600kW itself and operated up to 350kW routinely. The HPRF dummy load was stabilized with the change of the coolant. Preparation of 20MeV DTL HPRF test has been completed. LCP and PLC system for klystron power supply was already prepared. Voltage fluctuation was measured during klystron test. Voltage control feedback loop seems to be re-adjusted.

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Low Cycle Fatigue Characteristics of Duplex Stainless Steel with Degradation under Pure Torsional Load (순수 비틀림 하중하에서 열화를 고려한 2상 스데인리스강의 저주기 피로특성)

  • Gwon, Jae-Do;Park, Jung-Cheol
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.26 no.9
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    • pp.1897-1904
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    • 2002
  • Monotonic torsional and pure torsional low cycle fatigue(LCF) test with artificial degradation were performed on duplex stainless steel(CF8M). CF8M is used in pipes and valves in nuclear reactor coolant system. It was aged at 430$^{\circ}C$ for 3600hrs. Through the monotonic and LCF test, it is found that mechanical properties(i.e., yield strength, strain hardening exponent, strength coefficient etc.) increase and fatigue life(N$\sub$f/) decreases with degradation of material. The relationship between shear strain amplitude(${\gamma}$$\sub$a/)and N$\sub$f/ was proposed.