• Title/Summary/Keyword: magnetic core reactor

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Magnetic Core Reactor for DC Reactor type Three-Phase Fault Current Limiter

  • Kim, Jin-Sa;Bae, Duck-Kweon
    • International Journal of Safety
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    • v.7 no.2
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    • pp.7-11
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    • 2008
  • In this paper, a Magnetic Core Reactor (MCR) which forms a part of the DC reactor type three-phase high-Tc superconducting fault current limiter (SFCL) has been developed. This SFCL is more economical than other types with three coils since it uses only one high-Tc superconducting (HTS) coil. When DC reactor type three-phase high-Tc SFCL is developed using just one coil, fewer power electronic devices and shorter HTS wire are needed. The SFCL proposed in this paper needs a power-linking device to connect the SFCL to the power system. The design concept for this device was sprang from the fact that the magnetic energy could be changed into the electrical energy and vice versa. Ferromagnetic material is used as a path of magnetic flux. When high-Tc superconducting DC reactor is separated from the power system by using SCRs, this device also limits fault current until the circuit breaker is opened. The device mentioned above was named Magnetic Core Reactor (MCR). MCR was designed to minimize the voltage drop and total losses. Majority of the design parameters was tuned through experiments with the design prototype. In the experiment, the current density of winding conductor was found to be $1.3\;A/mm^2$, voltage drop across MCR was 20 V and total losses on normal state was 1.3 kW.

Analysis for Magnetic field generated in the Flux-Lock Type Reactor using HTSC during a fault time (고온초전도체를 이용한 자속구속 리액터의 사고시 발생되는 자계 분석)

  • Lim, Sung-Hun;Choi, Hyo-Sang;Kang, Hyeong-Gon;Ko, Seok-Cheol;Lee, Jong-Hwa;Choi, Myung-Ho;Song, Jae-Joo;Han, Byoung-Sung
    • Proceedings of the Korean Institute of Electrical and Electronic Material Engineers Conference
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    • 2003.07a
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    • pp.601-604
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    • 2003
  • The magnetic field generated in the iron core, which is required for the magnetic field to link each coil of the flux-lock type reactor, affects the fault current limiting characteristics of the flux-lock type high-Tc superconducting fault current limiter(SFCL). By applying numerical analysis for equivalent circuit of flux-lock type SFCL, the magnetic field induced in the iron core including currents of each coil was investigated. Through the analysis of magnetic field, we have analyzed that the magnetic field linked the 3rd coil, which is wound in the iron core, prevents the saturation of the iron core, but decreases the impedance of the flux-lock type SFCL.

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Design of the Magnetic Core Reactor for the connection to the Power System of DC Reactor Type High Temperature Superconducting Fault Current Limiter (DC 리액터형 고온초전도한류기의 전력계통 연계를 위한 자기철심리액터의 설계)

  • 임대준;배덕권;김호민;이찬주;윤경용;윤용수;고태국
    • Proceedings of the Korea Institute of Applied Superconductivity and Cryogenics Conference
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    • 2002.02a
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    • pp.322-325
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    • 2002
  • In this paper, the power-linking device connecting the high-Tc super-conducting(HTS) coil to the power system in the DC reactor type three-phase high-Tc superconducting fault current limiter (SFCL) has been designed. This design was triggered from the concept that the magnetic energy could be exchanged into the electrical energy each other. Ferromagnetic material is used as the path of magnetic flux. The device mentioned above was named Magnetic Core Reactor(MCR). MCR was designed to minimize the voltage drop caused by copper loss. The current density of the conductor was 1.3 A/mm$^2$ and % voltage drop was 2%.

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Design Optimization of CRDM Motor Housing

  • Lee, Jae Seon;Lee, Gyu Mahn;Kim, Jong Wook
    • Journal of Magnetics
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    • v.21 no.4
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    • pp.586-592
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    • 2016
  • The magnetic-jack type CRDM withdraws or inserts a control rod assembly from/to the reactor core to control the core reactivity. The CRDM housings form not only the path of the electromagnetic field but also the pressure boundary of a nuclear reactor, and a periodic in-service inspection should be carried out if there are welded or flange jointed parts on the pressure boundary. The in-service inspection is a time-consuming process during the reactor refueling, and moreover it is difficult to perform the inspection over the reactor head. A magnetic motor housing is applied for the current SMART CRDM and has several welding joints, however a nonmagnetic motor housing with fewer or no welding joints may improve the operational efficiency of the nuclear reactor by avoiding or simplifying the in-service inspection process. Prior to the development, the magnetic field transfer efficiency of the nonmagnetic housing was required to be assessed. It was verified and optimized by the electromagnetic analysis of the lifting force estimation. Magnetic flux rings were adopted to improve the efficiency. In this paper, the design and optimization process of a nonmagnetic motor housing with the magnetic flux rings for the SMART CRDM are introduced and the analyses results are discussed.

Investigation on high gradient magnetic separation for CRUD material in nuclear reactor

  • Shigehiro Nishijima;Naoki Nomura;Fumihito Mishima;Tomokazu Sekine
    • Progress in Superconductivity and Cryogenics
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    • v.26 no.3
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    • pp.5-8
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    • 2024
  • In this study, we investigated high-gradient magnetic separation as a method for separating crud in high-temperature, high-pressure water inside a nuclear reactor. Corrosion products in the coolant circulate through the system and attach to the reactor core, where they are activated by neutron irradiation. The activated corrosion products then desorb from the core and circulate through the cooling system again. The corrosion product in the reactor water or piping system is called crud. Crud is the main source of radiation exposure for radiation workers. Removal and recovery of crud is important in decommissioning plants that have been in operation for service life, and new technologies are also desired. A method for separating activated ions adsorbed on ion exchange resins in nuclear reactors using magnetic separation is developed. In this method, the ion exchange resin is washed with acid, the activated ions are adsorbed from the washing water using adsorbents, and then separated magnetically. Rudimentary experiments were conducted to investigate the possibility of this method.

Facility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap

  • Arzhannikov, Andrey V.;Shmakov, Vladimir M.;Modestov, Dmitry G.;Bedenko, Sergey V.;Prikhodko, Vadim V.;Lutsik, Igor O.;Shamanin, Igor V.
    • Nuclear Engineering and Technology
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    • v.52 no.11
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    • pp.2460-2470
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    • 2020
  • To study the thermophysical and neutronic properties of thorium-plutonium fuel, a conceptual design of a hybrid facility consisting of a subcritical Th-Pu reactor core and a source of additional D-D neutrons that places on the axis of the core is proposed. The source of such neutrons is a column of high-temperature plasma held in a long magnetic trap for D-D fusionreactions. This article presents computer simulation results of generation of thermonuclear neutrons in the plasma, facility neutronic properties and the evolution of a fuel nuclide composition in the reactor core. Simulations were performed for an axis-symmetric radially profiled reactor core consisting of zones with various nuclear fuel composition. Such reactor core containing a continuously operating stationary D-D neutron source with a yield intensity of Y = 2 × 1016 neutrons per second can operate as a nuclear hybrid system at its effective coefficient of neutron multiplication 0.95-0.99. Options are proposed for optimizing plasma parameters to increase the neutron yield in order to compensate the effective multiplication factor decreasing and plant power in a long operating cycle (3000-day duration). The obtained simulation results demonstrate the possibility of organizing the stable operation of the proposed hybrid 'fusion-fission' facility.

The Study of Designing the Parameters of DC Reactor for Inductive Superconducting Fault Current Limiter By Using Finite Element Method (유한요소법을 이용한 유도형 고온 초전도 한류기용 DC Reactor의 설계 파라미터 결정법에 관한 연구)

  • 김용구;강형구;김태중;윤용수;고태국
    • Proceedings of the Korea Institute of Applied Superconductivity and Cryogenics Conference
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    • 2002.02a
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    • pp.326-329
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    • 2002
  • The dc reactor type superconducting fault current limiter is composed of a power converter, magnetic core reactors and a do reactor that is a superconducting coil. When a fault occurs, the dc reactor maintains the stability of system by limiting its fault current. In this study, we focus on the design of the dc reactor using FEM(Finite Element Method). In order to design it, various elements should be considered such as magnetic field intensity, Lorentz's force, its inductance and so forth. Firstly, we forecast the values of those elements from the simulation of FEM and then measured with a copper wire magnet. Finally, verify the reliability of this FEM method by comparing with two results.

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Nano-sized Effect on the Magnetic Properties of Ag Clusters

  • Jo, Y.;Jung, M.H.;Kyum, M.C.;Park, K.H.;Kim, Y.N.
    • Journal of Magnetics
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    • v.11 no.4
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    • pp.160-163
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    • 2006
  • We have prepared crystalline Ag nanoparticles with an average size of 4 nm in diameter by using an inductively coupled plasma reactor equipped with the liquid nitrogen cooling system. Our magnetic data show that the nano-sized effect of Ag nanoparticles on the magnetic properties is ferromagnetic, instead of a diamagnetic component of the Ag bulk and a superparamagnetic component of magnetic nanoparticles. We have also studied the magnetic properties of Ag-Cu nanocomposites with an opposite concentration profile between surface and core. These comparisons indicate that the ferromagnetic component strongly depends on the surface of Ag nanoparticles, while the paramagnetic component is strongly affected by the outer oxide layer, with the background of a diamagnetic component from the core of Ag.

Robust technique using magnetohydrodynamics for safety improvement in sodium-cooled fast reactor

  • Lee, Jong Hui;Park, Il Seouk
    • Nuclear Engineering and Technology
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    • v.54 no.2
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    • pp.565-578
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    • 2022
  • Among Generation IV reactors, the sodium-cooled fast reactor (SFR) is attracting attention as a system having great potential for commercial use. Gas entrainment is a thermal-hydraulic issue related to the safety problem of the reactor core in the SFR. Typically, a dipped plate or baffles are installed under the free surface to suppress gas entrainment. However, these approaches can cause gas entrainment in other locations and require many trial-and-error and verifications. In this study, a new strategy using magnetohydrodynamics to suppress gas entrainment in the SFR is proposed. In a counter-flow model, a judgment criterion of gas entrainment occurrence was developed for both water and liquid metal. Moreover, the gas entrainment can be completely suppressed by applying a magnetic field.