• Title/Summary/Keyword: K-DEMO

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TOKAMAK REACTOR SYSTEM ANALYSIS CODE FOR THE CONCEPTUAL DEVELOPMENT OF DEMO REACTOR

  • Hong, Bong-Guen;Lee, Dong-Won;In, Sang-Ryul
    • Nuclear Engineering and Technology
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    • v.40 no.1
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    • pp.87-92
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    • 2008
  • Tokamak reactor system analysis code was developed at KAERI (Korea Atomic Energy Research Institute) and is used here for the conceptual development of a DEMO reactor. In the system analysis code, prospects of the development of plasma physics and the relevant technology are included in a simple mathematical model, i.e., the overall plant power balance equation and the plasma power balance equation. This system analysis code provides satisfactory results for developing the concept of a DEMO reactor and for identifying the necessary R&D areas, both in the physics and technology areas for the realization of the concept. With this system analysis code, the performance of a DEMO reactor with a limited extension of the plasma physics and technology adopted in the ITER design. The main requirements for the DEMO reactor were selected as: 1) demonstrate tritium self-sufficiency, 2) generate net electricity, and 3) achieve a steady-state operation. It was shown that to access an operational region for higher performance, the main restrictions are presented by the divertor heat load and the steady-state operation requirements.

DEMO: Deep MR Parametric Mapping with Unsupervised Multi-Tasking Framework

  • Cheng, Jing;Liu, Yuanyuan;Zhu, Yanjie;Liang, Dong
    • Investigative Magnetic Resonance Imaging
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    • v.25 no.4
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    • pp.300-312
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    • 2021
  • Compressed sensing (CS) has been investigated in magnetic resonance (MR) parametric mapping to reduce scan time. However, the relatively long reconstruction time restricts its widespread applications in the clinic. Recently, deep learning-based methods have shown great potential in accelerating reconstruction time and improving imaging quality in fast MR imaging, although their adaptation to parametric mapping is still in an early stage. In this paper, we proposed a novel deep learning-based framework DEMO for fast and robust MR parametric mapping. Different from current deep learning-based methods, DEMO trains the network in an unsupervised way, which is more practical given that it is difficult to acquire large fully sampled training data of parametric-weighted images. Specifically, a CS-based loss function is used in DEMO to avoid the necessity of using fully sampled k-space data as the label, thus making it an unsupervised learning approach. DEMO reconstructs parametric weighted images and generates a parametric map simultaneously by unrolling an interaction approach in conventional fast MR parametric mapping, which enables multi-tasking learning. Experimental results showed promising performance of the proposed DEMO framework in quantitative MR T1ρ mapping.

PRELIMINARY ESTIMATION OF ACTIVATED CORROSION PRODUCTS IN THE COOLANT SYSTEM OF FUSION DEMO REACTOR

  • Noh, Si-Wan;Lee, Jai-Ki;Shin, Chang-Ho;Kwon, Tae-Je;Kim, Jong-Kyung;Lee, Young-Seok
    • Journal of Radiation Protection and Research
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    • v.37 no.2
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    • pp.63-69
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    • 2012
  • The second phase of the national program for fusion energy development in Korea starts from 2012 for design and construction of the fusion DEMO reactor. Radiological assessment for the fusion reactor is one of the key tasks to assure its licensability and the starting point of the assessment is determination of the source terms. As the first effort, the activities of the coolant due to activated corrosion product (ACP) were estimated. Data and experiences from fission reactors were used, in part, in the calculations of the ACP concentrations because of lack of operating experience for fusion reactors. The MCNPX code was used to determine neutron spectra and intensities at the coolant locations and the FISPACT code was used to estimate the ACP activities in the coolant of the fusion DEMO reactor. The calculated specific activities of the most nuclides in the fusion DEMO reactor coolant were 2-15 times lower than those in the PWR coolant, but the specific activities of $^{57}Co$ and $^{57}Ni$ were expected to be much higher than in the PWR coolant. The preliminary results of this study can be used to figure out the approximate radiological conditions and to establish a tentative set of radiological design criteria for the systems carrying coolant in the design phase of the fusion DEMO reactor.

Comparisons and analysis on the prototype EU-DEMO TF CICC with Nb3Sn cable

  • Kwon, Soun Pil
    • Progress in Superconductivity and Cryogenics
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    • v.19 no.4
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    • pp.31-39
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    • 2017
  • European R&D on designing their version of a DEMO fusion tokamak has recently resulted in the testing of a prototype $Nb_3Sn$ Cable-in-Conduit Conductor (CICC) for the DEMO TF coil. The characteristics and reported results of low temperature performance tests with the prototype CICC sample are compared with those from CICC samples incorporating other recent $Nb_3Sn$ cable designs. The EU-DEMO TF CICC prototype shows performance characteristics similar to that of the ITER CS CICC with short twist pitch. This is a first for a CICC sample that does not have a circular cross section. Assessment of its internal magnetostatic self-field suggests that a reduction in the internal self-field due to the rectangular geometry of the EU-DEMO TF CICC prototype compared to one with a circular geometry may have contributed to the performance characteristics showing current sharing temperature ($T_{cs}$) initially increase then stabilize with repeated electromagnetic loading, similarly to ITER CS CICC results. However, constraints on the internal self-field are not a sufficient condition for this $T_{cs}$ characteristic to occur.

SEPARATION AND PURIFICATION PROCESS OF DEMO PLANT FOR 10TON PER DAY DME PRODUCTION (일일 10톤 DME 생산 Demo Plant에서의 분리정제 공정)

  • Ra Young Jin;Cho Wonihl;Shin Dong Geun;Lim Gye Gue
    • 한국가스학회:학술대회논문집
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    • 2005.10a
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    • pp.141-145
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    • 2005
  • DME (Di-Methyl Ether) is a new clean fuel and an environmental-friendly energy resource, also is recently increasing with an alternative interest because of the industrial use. DME has been shown to have excellent properties as a diesel fuel giving emission level better than ULEV standard. So it has been attracting considerable as an alternative diesel fuel. In this study, we carried out simulation of separation and purification process of demo plant for 101on per day DME production, which cause the effect that is important in productivity, from operation results of pilot plant for 50kg per day DME production. The liquefied stream, which was separated by gas-liquid separator after DME reactor, includes $CO_2$, DME, Methanol and $H_2O$. We established three distillation columns for separation and purification of the stream. $CO_2$ was extracted from the stream by first distillation column, DME was extracted by second column and Methanol was extracted by third column. We investigated and analyzed the effect which the actual operation variables cause in efficiency of process and optimized process, finally we got the DME of purity $100\%$.

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A Fault Section Detection Method for Ungrounded System Based on Phase Angle Comparison of Zero-Sequence Current (비접지 배전계통에서 영상전류 위상 비교에 의한 고장구간 검출 방법)

  • Yang, Xia;Choi, Myeon-Song;Lee, Seung-Jae
    • Proceedings of the KIEE Conference
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    • 2007.07a
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    • pp.31-32
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    • 2007
  • In this paper, a fault section detection method is proposed for ungrounded system in the case of a single line-to-ground fault. A conventional method is used for faulted feeder selection according to the angular relationship between zero-sequence currents of the feeders and zero-sequence voltage of the system. Fault section detection is based on the comparison of phase angle of zero-sequence current. Proposed method has been testified in a demo system by Matlab/Simulink simulations. Based on Distribution Automation System(DAS), Feeder Remote Terminal Unit(FRTU) is used to collect those necessary data, at present a demo system is under developing using Manufacturing Message Specification (MMS) in IEC61850 standard.

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Development of Anti-Rolling Demo System for Mobile Harbor Using Maglev Type AMD (자기부상방식 AMD를 이용한 모바일 하버용 횡동요 저감 데모 장비의 개발)

  • Park, Cheol-Hoon;Ham, Sang-Yong;Kim, Byung-In;Lee, Sung-Whee;Park, Hee-Chang;Cho, Han-Wook;Moon, Seok-Jun;Chung, Tae-Young
    • Journal of the Korean Society for Precision Engineering
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    • v.28 no.1
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    • pp.40-47
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    • 2011
  • Mobile harbor which is a novel concept of ocean transportation to bring the containers from the cargo ship waiting on the ocean away is being focused now. To provide the mobile harbor with the stable loading/unloading condition, it is necessary to develop the oscillation mitigation technologies such as anti-rolling system. Anti-rolling system using AMD(Active Mass Driving) has merits that it can handle the disturbances more actively and mitigate the rolling oscillation faster than other type anti-rolling system. However, rack-and-pinion type AMD has problems such as big friction noise from gears and motor, wear and tear, and continuous maintenance. In this paper, novel anti-rolling system using Maglev type AMD for mobile harbor is suggested in order to resolve the problems caused by the friction. This novel anti-rolling system doesn't make any friction because it supports the moving mass by using magnetic levitation force and moves it by using propulsion force from the linear motor. The demo system of the novel anti-rolling system using maglev type AMD has been developed in order to investigate its feasibility. This paper presents the procedures and results of development of this demo system.

Development of Large-Area RF Ion Source for Neutral Beam Injector in Fusion Devices

  • Chang, Doo-Hee;Jeong, Seung Ho;Kim, Tae-Seong;Park, Min;Lee, Kwang Won;In, Sang Ryul
    • Proceedings of the Korean Vacuum Society Conference
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    • 2013.08a
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    • pp.179.2-179.2
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    • 2013
  • A large-area RF-driven ion source is being developed at Germany for the heating and current drive of ITER device. Negative hydrogen ion sources are major components of neutral beam injection (NBI) systems in future large-scale fusion experiments such as ITER and DEMO. The RF sources for the production of positive hydrogen ions have been successfully developed at IPP (Max-Planck-Institute for Plasma Physics), Garching, for the ASDEX-U and W7-AS neutral beam heating systems. Ion sources of the first NBI system (NBI-1) for the KSTAR tokamak have been developed successfully with a bucket plasma generator based on the filament arc discharge, which have contributed to achieve a good plasma performance such as 15 sec H-mode operation with an injection of 3.5 MW NB power. There is a development plan of RF ion source at the KAERI to extract the positive ions, which can be used for the second NBI system (NBI-2) of the KSTAR and to extract the negative ions for future fusion devices such as Fusion Neutron Source and Korea-DEMO. The development progresses of RF ion source at the KAERI are described in this presentation.

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A Study on the Coping Behaviors with Economic Crisis of Korean Households (한국 가계의 경제위기 대처행동에 관한 연구)

  • Lee, Kyoung-Ok;Jung, Yong-Sun
    • Korean Journal of Human Ecology
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    • v.8 no.1
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    • pp.81-93
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    • 1999
  • Now in Korea, many households are facing with economic crisis. The study based on the premise that household economic status could keep as stable as before economic crisis depending on the coping behavior of housewives as a manager of household. The purpose of this study was to find the coping behavior patterns with economic crisis of housewives, and to examine the socio-demo-economic factors which influence the coping behavior with economic crisis of housewives. Major findings were as follows; (1) The principal two patterns of coping with economic crisis were active coping behavior and passive coping behavior. (2) The most frequently used coping behavior pattern was passive coping behavior. (3) The patterns of coping with economic crisis were influenced by the socio-demo-economic factors.

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