Results 281 to 290 of about 138,513 (347)

Thermal Control of Ceramic Breeder Blankets

Fusion Technology, 1993
AbstractThermal control is an important issue for ceramic breeder blankets since the breeder needs to operate within its temperature window for the tritium release and inventory to be acceptable. A thermal control region is applicable not only to situations where the coolant can be run at low temperature, such as for the International Thermonuclear ...
A. René Raffray, Mark S. Tillack, Mohamed A. Abdou   +2 more
openaire   +1 more source

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
openaire   +1 more source

Neutronics effects of homogeneous model on solid breeder blanket of CFETR

, 2020
In the design of solid breeder blanket, normally the homogenous model is used for the neutronics analysis to assess the performance of blanket, but the adaptability of homogenous model is neglected.
Shen Qu, Q. Cao, X. Duan, Xueren Wang, Zaixin Li, Xiaoyu Wang   +5 more
semanticscholar   +1 more source

Thermo-mechanical assessment of the optimized CFETR water cooled ceramic breeder blanket

Fusion engineering and design, 2020
The Water Cooled Ceramic Breeder (WCCB) blanket is one of the candidates for Chinese Fusion Engineering Test Reactor (CFETR). Within the framework of the engineering design of CFETR, an updated design of WCCB blanket was proposed corresponding to the ...
Xuebin Ma, Xiaoman Cheng, Songlin Liu, Kai Huang   +3 more
semanticscholar   +1 more source

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

Neutronics influence of poloidal nonuniform neutron wall loading on helium-cooled ceramic breeder blanket for CFETR

, 2020
After its conceptual design, the Chinese Fusion Engineering Test Reactor (CFETR) is now at the stage of detailed engineering design. During this stage, many detailed factors should be considered for the components in the CFETR.
Qiang Lian, W. Tian, S. Qiu, G. Su
semanticscholar   +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
openaire   +1 more source