Results 261 to 270 of about 9,751 (308)

Fusion Breeder Blanket Design Considerations

Nuclear Technology - Fusion, 1983
The Fusion Breeder Program is a DOE funded program directed by Lawrence Livermore National Laboratory; the other participants in this hybrid fusion reactor design are TRW Company, GA Technologies Inc., Westinghouse Corporation, and Oak Ridge National Laboratory.
C. P. C. Wong, R. L. Creedon, I. Maya, K. R. Schultz   +3 more
openaire   +1 more source

Ceramic Breeder Blanket for ARIES-CS

Fusion Science and Technology, 2005
This paper describes the conceptual design of a ceramic breeder blanket considered as one of the candidate blankets in the first phase of the ARIES-CS study. The blanket is coupled to a Brayton power cycle to avoid the safety concern associated with the possibility of Be/steam reaction in case of accident.
A. R. Raffray, S. Malang, L. El-Guebaly, X. Wang   +3 more
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Thermal control of solide breeder blankets

Fusion Engineering and Design, 1991
Abstract An assessment of the thermal control mechanisms applicable to solid breeder blanket designs under ITER-like operating conditions is presented in this paper. Four cases are considered: a helium gap; a sintered block Be region; a sintered block Be region with a metallic felt at the Be-clad interface; and a Be packed bed region. For these cases,
Raffray, A. R., Ying, A., Gorbis, Z., Tillack, M. S., Abdou, M. A.   +4 more
openaire   +1 more source

Breeder and test blankets in ITER

Fusion Engineering and Design, 1991
Abstract An overview of ITER efforts is presented in this paper in the area of blanket development and ITER test program preparation. The design of ceramic and eutectic options of the driver blanket were developed aimed on a reliable operation and adequate tritium production.
G.E. Shatalov, M.A. Abdou, A. Antipenkov, W. Daenner, Y. Gohar, T. Kuroda, G. Simbolotti, D.L. Smith, N. Yoshida   +8 more
openaire   +1 more source

Solid breeder blanket design and tritium breeding

Fusion Engineering and Design, 1991
Abstract Thermonuclear D–T power plants will have to be tritium self-sufficient. In addition to recovering the energy carried by the fusion neutrons (about 80% of the fusion energy), the blanket of the reactor will thus have to breed tritium to replace that burnt in the fusion process.
Proust, E., Anzidei, L., Dalle Donne, M., Fischer, U., Kuroda, T.   +4 more
openaire   +1 more source

DUAL COOLANT LIQUID METAL BREEDER BLANKET

1993
A blanket concept for a fusion DEMO-reactor combining self-cooling of the liquid metal breeder zone with helium-cooling of the first wall is described. Main emphasis has been placed on high safety and reliability features and on a simple, stiff blanket structure.
Malang, S., Bojarsky, E., Buehler, L., Deckers, H., Fischer, U., Norajitra, P., Reiser, H.   +6 more
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Development of ceramic breeder blankets in Japan

Fusion Engineering and Design, 1998
Ceramic breeding blankets are the main options for DEMO reactor designs in JAERI, and large efforts have been made in the area of related materials development, engineering-scaled R&D, as well as design development. A long-term R&D program was launched in 1996 to provide an engineering database and fabrication technologies for the DEMO blanket and its ...
H. Takatsu, H. Kawamura, S. Tanaka
openaire   +1 more source

Helium-Cooled, Flibe Breeder, Beryllium Multiplier Blanket

Fusion Technology, 1985
The concept described for the blanket surrounding a fusion reaction chamber is based on the use of molten fluoride salts to convert fusion energy into electricity and to breed the tritium fuel for the fusion power plant. Helium cools the first-wall and the blanket internals, which consist of a bed of beryllium balls in which neutrons are multiplied ...
Ralph W. Moir, Joseph D. Lee, R. Carroll Maninger, William S. Neef, Albert E. Sherwood, David H. Berwald, Jackson H. DeVan, Jungchung Jung   +7 more
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Helium-Cooled Solid Breeder Blanket for ITER

Fusion Technology, 1989
This paper summarizes the latest results of a design study of a helium-cooled solid breeder blanket for ITER.
A. R. Raffray, M. A. Abdou, P. Chou, Z. Gorbis, M. Tillack, Y. Watanabe, A. Ying   +6 more
openaire   +1 more source

Development of Solid Breeder Blanket at JAERI

Fusion Science and Technology, 2005
Japan Atomic Energy Research Institute (JAERI) has been performing blanket development based on the long-term research program of fusion blankets in Japan, which was approved by the Fusion Council of Japan in 1999. The blanket development consists of out-pile R and D, In-pile R and D, TBM Neutronics and TPR Tests and Tritium Recovery System R and D ...
Mikio Enoeda, Toshihisa Hatano, Kunihiko Tsuchiya, Kentaro Ochiai, Yoshinori Kawamura, Kimio Hayashi, Takeo Nishitani, Masataka Nishi, Masato Akiba   +8 more
openaire   +1 more source