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6 SUMMARY I. Title Establishment of KAERI Strategy and Organization for Fusion Power Technology Research II. Objective and Importance of the Project This project aims at establishment of a KAERI strategy and organization for fusion power technology research on a long-term time scale, over years of time into the future. This includes detailed near-term R&D planning for those immediately necessary activities such as breeder blanket, tritium technologies, and power plant concept studies. Nuclear fusion is widely considered as an ideal future nuclear energy that is environmentally acceptable, suitable for large-scale electricity production for commercial purpose, and sustainable for its minimal consumption of natural resources. Over 50 years of fusion research worldwide has led us to the construction of International Thermonuclear Experimental Reactor (ITER), which is expected to start in KAERI has been the national institute for researches in the peaceful utilization of nuclear energy since 1959, with advanced technological and human resources in nuclear engineering as well as in other science, technologies, and policy studies. This excellent research assets enable KAERI to develop fusion power technologies efficiently and systematically, through strategic relocation and coordination of its resources. In this regard, therefore, Korea's participation in ITER in mandates a leading role by KAERI in supplying the negotiated nuclear components of ITER, such as shield blanket modules, tritium plant, and so on, in addition to the planned breeder blanket test experiments. This in return requires KAERI a feasible and verifiable strategy and long-term plan for fusion power technology development, as well as immediately necessary researches for current issues such as breeder blanket and power plant concepts. Such a plant-oriented, engineering-intensive fusion energy research will lead Korea most efficiently to (1) the establishment of technological basis for the critical long-term national autonomy in energy, and (2) succesful participation in ITER project which will allow Korea to join in the group of countries with advanced fusion power technologies. Such a vision is an essential ingredient of the "KAERI Vision 2020" toward a sustainable nuclear energy, technology, and industry in Korea. III. Contents and Scope of the Project (1) Establishment of a long-term R&D strategy for nuclear fusion energy (2) A mid-term planning for R&D in power plant conceptual design studies and
7 necessary core technologies, in compliance with KAERI Vision IV. Results and Proposal for Its Utilization (1) Results A three-stage, 45 years long, R&D strategy and research plan that aims construction, operation, and demonstration of a commercially meaningful large-scale electricity production through a demonstration fusion power reactor (tentatively designated as 'KDEMO') is derived and proposed. Each stage includes following R&D activities: The 10-year first stage aims at successful preparation for the ITER test blanket test experiment. Korean breeder blanket concepts and their test modules (KTBM) are developed, and ex-pile tests are completed. In parallel to this, conceptual design study of KDEMO fusion power plant and other related activities are performed to support the KTBM development process. The 15-year second stage aims at (1) successful completion of ITER test blanket experiments and finalization of KDEMO blanket design, (2) completion of the engineering design of the KDEMO power plant, which includes magnets, divertor, breeder blanket, fuel cycle, and BOP. The 20-year third stage aims at the construction and operation of the KDEMO power plant. If an international DEMO project is decided and materialized, then KDEMO construction/operation will have to be replaced by such international DEMO project and related activities. (2) Proposed utilization of the results Proposed plans are to be immediately started, even as a temporary intramural project, to meet those urgent R&D needs mandated by the ITER project, especially ITER schedules for Test Blanket experiments. A concurrent, in-depth discussion/review and coordination of the proposed plan is necessary, among the related organizations including the government, KAERI, and other related institutes/industries. The process must be started immediately and a decision thereof must be reached as soon as possible.
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9 CONTENTS Part I. Feasibility Study of the Project...1 Part II. Project Overview: Development of the Korean Demonstration Fusion Power Plant (KDEMO) Part III. Detailed R&D Plan for the First 10 Years Acknowledgement for Mr Scott Sharick of Honolulu, USA, whose permission to use his photograph of a magnificent Hawaiian sunset made the cover design of this report possible. Photo Scott Sharick. The fusion power plant schematic diagram in the cover is from the JET brochure, published in 2004 by EFDA, European Union.
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31 Fueling Fuel management Fuel inline storage Tritium shipment/permanent storage Plasma Plasma exhaust processing FW coolant processing Impurity separation Impurity processing Isotope separation system Plasma Facing Component Solid waste PFC Coolant Blanket Coolant processing Coolant tritium recovery system Tritium waste treatment (TWT) Water stream and air processing waste Breeder Blanket Blanket tritium recovery system Only for solid breeder or liquid breeder design using separate coolant Only for liquid breeder as coolant design
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80 샘펀- g ιc 으 Q 근; c υ버 > i = ---- wi a gi ~ ~ C 으 α q ι= 3-5 (드훌i활 환 ~ m E 융 Q C 훌콰뚫흩 υ 인인반에디 대펀~ τ인- c e 잉을a 드잉Q b = g gi c Q 응t2a --c ~ α ~ 그 - ~ "'".. -~Z! ω --α ι;e 영홍 음 E ω
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91 WBS Procurement Packages Direct Capital Cost (kiua) 참여율 (%) US M$ 1.1 Magnet Systems 6. Conductor 6 A) TF Vacuum Vessel 1 Main Vessel 1 A) Sectors + Bl Manifold A) equat + NB ports Port Assemblies 2 B) upper ports +? VV Supports C) lower ports Blanket System 2.2 Machine Assembly 3.2 Tritium Plant 4.1 Power Supplies 1. FW/Blanket Shield Modules 2. Assembly Tooling 2. Storage & Delivery, Long Term Storage System 2. AC/DC Converters 1 A) FW (Incl Be) B) Shield A) Ass tools (n. 3 to 11) Diagnostics TBD 합계 390.3
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106 Electricity α duction [EJe 1 갱." ",., " s,. 口 ~ WlNO TURBltlES 口 ~ ~. 잉Æ 口 FUSION~ fi 口 "~~ 디.ru.~.'"ι 口 "~, !XID D E a끼 ty PI 1 a '" a 6010 {EJeJ 디 x ^' 口..,. ".- 口 '" i,." 디.".. 口 g 애 口 ""'" i Stabiliz at iol' ge l C02 (ppm] Eleetriclty α <l uction (EJe] g '" g " " 0 口 π 口 "'"κ""" - "'" 口 ""'... 디 """
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154 KDEMO KDEMO-A KDEMO-B
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158 응C Z ω ; 이으 2 ω응; s υ> α< Z ---- 버αα, 임 딩 R 써 딩 Q R ~ ; i c g; e 1csg 녀떠펴많 ; 편떨 i 냥뚫흐 φζf 3 드g Q b > 응 응을a 응c F 이응3 j g it5a i q υl s 떼인이윈티인에디R ~ ~ 딩 m 므 ~ ~ ζf m 응등3 g 니ζS 이 4 딩 m > m g N., i S g - ι. i sg L니 - > " L 니 ; E -
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173 Projects L1 - Central Solenoid Model Coil L2 - Toroidal Field Model Coil L3 - Vacuum Vessel Sector L4 - Blanket Module L5 - Divertor Cassette L6 - Blanket Module Remote Handling L7 - Divertor Remote Handling EU Share of the Total Value (%) é é
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224 λ ( 2.7 ± 0.3) W mk pebble = / 4 λpebble bed = T W / mk
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230 Li Be Size Li 세라믹페블미세조직제어 PIE (TMS )
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234 / ( ) MHD / ( )
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259 블랭킷개념설계 설계코드및설계방법수립 기본설계완료 DDD 생산 설계 database 축적 설계모델분석및평가 상세설계 상세설계 submodule 시험용설계보고서생산 DDD 개정 DDD ITER test port 공유방안 국내시험계획수립 TBM 상세시험계획수립 ITER 시험인허가획득 TBWG 참여 신기술자료수집 TBWG 참여 ITER 시험인허가획득 Electro-magnetic submodule 일차벽 ( 소형 ) 가공기술개발 기타부품기술시방개발 페블제조기술개발 페블가공방법개량 일차벽 ( 중형 ) 가공기술개발 페블및일차벽특성시험 E-M submodule 제작및관련 QA/QC 문서생산
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270 10-30 Emissivity (W m 3 ) He Be C Ne Ar Kr W H (ev) T e
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349 TAURO, '96 ARIES-I ARIES-AT DREAM, '97 Normal operation Fusion power Electrical power Net efficiency Blanket lifetime Mode of operation Plasma geometry Major plasma radius Aspect ratio Wall loads (FW, divertor) Max. FW surf. heat flux Max. Div. surf. heat flux Avg. Neutron Wall load In-vessel components Structural material Breeding material Neutron multiplier Coolant Coolant inlet/outlet temp. FW protection 3000MW 1000MW 45% 5 years continuous 9.4m MW/m 2 5MW/m 2 2MW/m 2 SiC/SiC Pb-17Li - Pb-17Li, 2MPa 450/860 SiC (CVD) 1925MW 1000MW 49% 7.2 years continuous 6.75m MW/m 2 4.5MW/m 2 2.5MW/m 2 SiC/SiC Li 2ZrO 3 Be He, 10MPa 350/650 SiC (CVD) 1719MW 1000MW 59% 2 years continuous 5.2m 4 0.7MW/m 2 5MW/m 2 4.3MW/m 2 SiC/SiC Pb-17Li Pb-17Li, 1MPa 650/1100 SiC (CVD) 5500MW 3000MW >45% <4 years continuous 16m 8 0.5MW/m 2 5MW/m 2 3MW/m 2 SiC/SiC Li 2O Be He, 10MPa 600/900 SiC (CVD)
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380 [Length] m [Mechanical properties] - embrittlement, hardening, toughness Dislocation Dynamics µm [Microstructural features] - number density, size distribution, volume fraction, structure and composition Kinetic Monte Carlo nm Molecular Dynamics Nuclear reaction [Damage production] - primary damage state - distribution of point defects & their clusters ps ms sec [Time]
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레이아웃 1
FUSION NOW 2012 SPRING 에너지 작합니다. 의 꿈 시 꿈꿔온 소에서 구 인류가 연 융합 국가핵 대전광역시 유성구 과학로 169-148 Tel_042)879-6000 FAX_042)879-6977 http://www.nfri.re.kr http://m.nfri.re.kr/ Twitter : @kstar_iter Facebook : /fusionnow
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Sejong University 2016 2016 Sejong University 4 SEJONG UNIVERSITY www.sejong.ac.kr 5 8 SEJONG UNIVERSITY 2016 Sejong University 10 SEJONG UNIVERSITY www.sejong.ac.kr 11 12 SEJONG UNIVERSITY www.sejong.ac.kr
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수시과제 2015-13 경기도 지역별 여성일자리 정책 추진 전략 연구책임자 : 최 윤 선 (본원선임연구위원) : 남 승 연 (본원연구위원) 연 구 지 원 : 이 상 아 (본원위촉연구원) 연 구 기 간 : 2015. 9 ~12 2015 발 간 사 여성 일자리는 사회 내 여성과 남성간의 차이를 좁히고 개개인의 삶을 윤택하게 만드는 중요 한 부분입니다. 이에 정부는
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connect educational content with entertainment content and that production of various contents inducing educational motivation is important. Key words: edutainment, virtual world, fostering simulation
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