Development of solid breeder blanket at jaeri

Fusion Science and Technology

Volumn 47, Issue 4, 2005, Pages 1060-1067

  Enoeda, Mikio ^a   Hatano, Toshihisa ^a   Tsuchiya, Kunihiko ^a   Ochiai, Kentaro ^a   Kawamura, Yoshinori ^a   Hayashi, Kimio ^a   Nishitani, Takeo ^a   Nishi, Masataka ^a   Akiba, Masato ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

FUSION REACTIONS; MARTENSITE; MOCKUPS; NUCLEAR ENGINEERING; NUCLEAR REACTOR REFLECTORS; PILES; RESEARCH AND DEVELOPMENT MANAGEMENT;

JAPAN ATOMIC ENERGY RESEARCH INSTITUTE (JAERI); NEUTRON REFLECTORS; NEUTRONICS; TRITIUM RECOVERY SYSTEM;

BREEDING BLANKETS;

EID: 18744407351     PISSN: 15361055     EISSN: None     Source Type: Journal    
DOI: 10.13182/fst05-a827     Document Type: Conference Paper

References (25)

1. S. KONISHI, et al., " DEMO plant design beyond ITER", Fusion Engineering and Design, 63-64 (2002) 11-17.
2. S. Mori, et al., " Blanket and divertor design for the Steady State Tokamak Reactor (SSTR)", Fusion Engineering and Design, 18 (1991) 249-258.
3. M. ENOEDA et al., " Design and technology development of solid breeder blanket cooled by supercritical water in Japan", Nuclear Fusion, volume 43, issue 12, pages 1837-1844 (2003) and http://stacks.iop.org/0029-5515/ 43/1837
4. H. MIURA, et al., " Design of Test Blanket System for ITER Module Testing", JAERI-Tech 97-051 (1997).
5. M. ENOEDA, et al., " Design and Development of Ceramic Breeder Demo Blanket", IAEA-CN-69, 17th Fusion Energy Conference, Yokohama, Japan, 19-24 October 1998, FTP/29(1998).
6. M. TAMURA et al., " Phase Stability of Reduced Activation Ferritic Steel: 8%Cr-2%W-0.2%V-0.04%Ta-Fe", J. Nucl. Mater., 155-157 (1988) 620
7. S. JITSUKAWA et al., " Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H", J. Nucl. Mater., 307-311, (2002) 179-186.
8. K. SHIBA, et al., " Reduced activation martensitic steels as a structural material for ITER test blanket", J. Nucl. Mater., 329-333, (2004) 243-247.
9. M. ODA et al., " Development of HIP Bonding Procedure and Mechanical Properties of HIP Bonded Joints for Reduced Activation Ferritic Steel F-82H", JAERI-Tech 97-013, (1997).
10. T. HATANO et al., " High heat flux test of a HIP-bonded first wall panel of reduced activation ferritic steel F-82H", J. Nucl Mater., 283-287 (2000) 685
11. T. HIROSE, et al., " Effects of Heat Treatment Process for Blanket Fabrication on Mechanical Properties of F82H", J. Nucl. Mater., 329-333 (2004) 324-327.
12. M. ENOEDA et al., " Effective Thermal Conductivity Measurements of the Binary Pebble Beds by Hot Wire Method for the Breeding Blanket", Fusion Technol., 34, 877-881 (1998).
13. M. ENOEDA et al., " Effective Thermal Conductivity Measurement of the Candidate Ceramic Breeder Pebble Beds By the Hot Wire Method", Fusion Technol., 39, 612-616 (2001)
14. T. HATANO, et al., " Effective thermal conductivity of a Li2TiO3 pebble bed for a DEMO blanket", Fusion Science and Technology, 44, pp94-98(2003)
15. 3 pebble bed", to be appeared in 23rd SOFT, 20-24 Sept. 2004, Venice, Italy, (2004).
16. 3 Pebbles by Wet Process", J. Ceram. Soc. Japan, Supplement, 112, S183-S186 (2004).
17. 3 Being Added with Oxide", presented at 2004 Spring Meeting of Atomic Energy Soc. Japan, March 29-31, 2004, Okayama, Japan, 1-40.
18. H. KAWAMURA et al., " Status of Beryllium R&D in Japan", Proc. 6th Int. Workshop on Beryllium Technology for Fusion, Dec. 2-5, 2003, Miyazaki City, Japan; JAERI-Conf. 2004-006, 26 (2004).
19. M. UCHIDA et al., " Elementary Development of Beryllide Pebble Fabrication by Rotating Electrode Method", Fusion Eng. Des., 69, 491 (2003).
20. 3 Pebble Bed in Japan", J. Nucl. Sci. Technol., 38, 996 (2001).
21. 3 Pebbles", Fusion Eng. Des., 51-52, 887 (2000).
22. S. Sato, et. al., to be presented in this conference.
23. th International Workshop on Ceramic Breeder Blanket Interactions, Tokyo, Japan, Dec. 15-17 (2003), JAERI-Conf 2004-012, p.215, Japan Atomic Energy Research Institute (2004).
24. M. ENOEDA et al., " Recovery of tritium by cryogenic molecular sieve bed in breeding blanket interface condition," Fusion Technol., 26, 664 (1994).
25. Y.KAWAMURA et al., " Extraction of hydrogen from water vapor by hydrogen pump using ceramic protonic conductor," Fusion Sci. Technol., 45, 33 (2004).