CURRENT R&D ACTIVITIES ON KOREAN HELIUM COOLED SOLID BREEDER TEST BLANKET MODULE

被引:7
作者
Cho, Seungyon [1 ]
Ahn, Mu-Young [1 ]
Ku, Duck Young [1 ]
Kim, Duck Hoi [1 ]
Yu, In-Keun [1 ]
Han, Seunghee [2 ]
Kim, Dong-Ik [2 ]
Yoon, Han-Ki [3 ]
Lee, Sang-Jin [4 ]
机构
[1] Natl Fus Res Inst, Taejon 305333, South Korea
[2] Korea Inst Sci & Technol, Seoul, South Korea
[3] Dong Eui Univ, Pusan, South Korea
[4] Mokpo Natl Univ, Muan, South Korea
关键词
MARTENSITIC STEEL;
D O I
10.13182/FST09-A8905
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Helium Cooled Solid Breeder (HCSB) blanket is one of two blanket concepts being considered as Korean Test Blanket Module (TBM) for ITER with the aim for testing and verifying the capability of the breeding blanket concepts. R&D activities being carrying out for HCSB TBM include the development of materials, fabrication technologies, and TBM associated system design. A small sample of ferritic/martensitic (FM) steel was fabricated. It was found that the tensile strength was close to previous value. A fabrication technique of sphere pebbles of lithium titanate breeder and graphite reflector was developed. A FM/FM TIG welding was performed and the results showed that tensile strength of the welded zone was decreased about 10%. A small punch test method of mechanical property evaluation was introduced to verify the suitability of small specimen for irradiation test by examining the relationship of the conventional uniaxial tensile test, and the tensile strengths were compared. As TBM design has complicated square channel configuration, short square channel was fabricated successfully. Finally, the components and specifications of the TBM associated systems are described in this paper.
引用
收藏
页码:216 / 220
页数:5
相关论文
共 8 条
[1]  
CHO S, 2008, FUSION ENG IN PRESS
[2]   Current status of design and analysis of Korean Helium-Cooled Solid Breeder Test Blanket Module [J].
Cho, Seungyon ;
Ahn, Mu-Young ;
Kim, Duck Hoi ;
Lee, Eun-Seok ;
Yun, Sunghwan ;
Cho, Nam Zin ;
Jung, Ki Jung .
FUSION ENGINEERING AND DESIGN, 2008, 83 (7-9) :1163-1168
[3]   He bubble growth in a martensitic steel for fusion reactors [J].
Coppola, R ;
Magnani, M ;
May, RP ;
Moeslang, A .
JOURNAL OF APPLIED CRYSTALLOGRAPHY, 2000, 33 (01) :469-472
[4]   Joining technologies of reduced activation ferritic/martensitic steel for blanket fabrication [J].
Hirose, T ;
Shiba, K ;
Ando, M ;
Enoeda, M ;
Akiba, M .
FUSION ENGINEERING AND DESIGN, 2006, 81 (1-7) :645-651
[5]   Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H [J].
Jitsukawa, S ;
Tamura, M ;
van der Schaaf, B ;
Klueh, RL ;
Alamo, A ;
Petersen, C ;
Schirra, M ;
Spaetig, P ;
Odette, GR ;
Tavassoli, AA ;
Shiba, K ;
Kohyama, A ;
Kimura, A .
JOURNAL OF NUCLEAR MATERIALS, 2002, 307 (1 SUPPL.) :179-186
[6]   Highly sinterable lithium titanate powders fabricated by an organic-inorganic solution route [J].
Lee, Myung Hyun ;
Jung, Choong-Hwan ;
Lee, Sang Jin .
ADVANCES IN NANOMATERIALS AND PROCESSING, PTS 1 AND 2, 2007, 124-126 :807-+
[7]   Reduced activation martensitic steels as a structural material for ITER test blanket [J].
Shiba, K ;
Enoeda, M ;
Jitsukawa, S .
JOURNAL OF NUCLEAR MATERIALS, 2004, 329 :243-247
[8]  
TANIGAWA H, 2007, 8 INT S FUS NUCL TEC