Filters
Results 1 - 10 of 10724
Results 1 - 10 of 10724.
Search took: 0.029 seconds
Sort by: date | relevance |
Sagara, A.; Motojima, O.; Watanabe, K.
Third international symposium on fusion nuclear technology1994
Third international symposium on fusion nuclear technology1994
AbstractAbstract
[en] Conceptual design of blanket and divertor for a force free helical reactor (FFHR) is presented. The DEMO relevant FFHR is heliotron type helical reactor having super conducting helical and poloidal coils based on the Large Helical Device (LHD) which is now under construction in NIFS. The main features of FFHR are (1) force free configuration of helical coils to reduce the total structural mass required for magnetic energy, (2) plasma operation with no current disruptions, (3) steady-state operation with a small fraction of the recirculating power. For the goal of a self-ignited D-T reactor of 3 GW thermal output, the design parameters for FFHR are investigated under the LHD scaling for energy confinement and density limit. In particular, to satisfy the reactor lifetime of 30 years, the engineering issues in FFHR are discussed by focusing on the following aspects; neutron wall loading as low as about 1.5 MW/m2, tritium breeding with nuclear heating, cooling with liquid coolant and operation temperature in the blanket, selection of structural materials with low activation, radiation shielding to achieve more that 5 order reduction at super conducting coils, configuration of high heat flux components in divertor regions, helium ash removal with the efficiency around 30%, and safety
Primary Subject
Secondary Subject
Source
Anon; 362 p; 1994; p. 83; University of California; Los Angeles, CA (United States); ISFNT-3: international symposium on fusion nuclear technology; Los Angeles, CA (United States); 27 Jun - 1 Jul 1994
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The design of blankets for NET is reviewed. Three categories of blankets are discussed: non breeding shield blankets for the physics phase, tritium producing driver blankets to operate the NET machine for extended periods of time in the technology test phase, and DEMO relevant blankets, which shall demonstrate their performance as test modules in NET. This separation of functions has only recently been determined as have been the definitions for DEMO load conditions. The evolution of the different blanket concepts is described with emphasis on design characteristics and supporting RD. particular ITER aspects are complemented. (author). 36 refs.; 16 figs.; 3 tabs
Primary Subject
Source
Ingen, A.M. van; Nijsen-Vis, A. (Associatie Euratom-FOM, Nieuwegein (Netherlands). FOM-Instituut voor Plasmafysica); Klippel, H.T. (Netherlands Energy Research Foundation, Petten (Netherlands)) (eds.); 937 p; ISBN 0 444 87369 4;
; 1989; p. 101-114; North-Holland; Amsterdam (Netherlands); 15. Symposium on fusion technology; Utrecht (Netherlands); 19-23 Sep 1988

Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] China focuses on the development of the liquid LiPb blanket due to its attractive performances. A series of LiPb breeder blanket concepts were proposed for different applications of fusion in China. This paper gives an overview of the LiPb breeder blanket concepts and relevant R and D progress in China.
Primary Subject
Source
SOFT-26: 26. symposium on fusion technology; Porto (Portugal); 27 Sep - 1 Oct 2010; S0920-3796(10)00581-8; Available from http://dx.doi.org/10.1016/j.fusengdes.2010.12.046; Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Literature Type
Conference
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] This paper recalls the main features of the TAURO blanket, a self-cooled Pb-17Li concept using SiC/SiC composites as structural material, developed for FPR. The objective of this design activity is to compare the characteristics of present-day industrial SiC-SiC composites with those required for a fusion power reactor blanket (FPR) and to evaluate the main needs of further R and D. The performed analyses indicated that the TAURO blanket would need the availability of SiC/SiC composites approximately 10 mm thick with a thermal conductivity through the thickness of approximately 15 Wm-1K-1 at 1000 C and a low electrical conductivity. A preliminary MHD analysis has indicated that the electrical conductivity should not be greater than 500 Ω-1m-1. Irradiation effects should be included in these figures. Under these conditions, the calculated pressure drop due to the high Pb-17Li velocity (approximately 1 m s-1) is much lower then 0.1 MPa. The characteristics and data base of the recently developed 3D-SiC/SiC composite, Cerasep trademark N3-1, are reported and discussed in relation to the identified blanket design requirements. The progress on joining techniques is briefly reported. For the time being, the best results have been obtained using Si-based brazing systems initially developed for SiC ceramics and whose major issue is the higher porosity of the SiC/SiC composites. (orig.)
Primary Subject
Source
4. international symposium on fusion nuclear technology (ISFNT-4); Tokyo (Japan); 6-11 Apr 1997; 10 refs.; Part B
Record Type
Journal Article
Literature Type
Conference
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Malang, S.; Reimann, J.; Baleron, L.; Mueller, U.
The seventh international Beer Sheva seminar on MHD flows and turbulence1993
The seventh international Beer Sheva seminar on MHD flows and turbulence1993
AbstractAbstract
[en] Short communication
Primary Subject
Source
Anon; 168 p; Feb 1993; p. 88; 7. international Beer Sheva seminar on MHD flows and turbulence; Jerusalem (Israel); 14-18 Feb 1993
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Published in summary form only
Original Title
Anlagentechnische Voraussetzungen fuer den flexiblen Einsatz von Test-Blankets in der NET-Fusionsanlage
Primary Subject
Source
Deutsches Atomforum e.V., Bonn (Germany, F.R.); Kerntechnische Gesellschaft e.V., Bonn (Germany, F.R.); 789 p; May 1988; p. 683-686; INFORUM Verl; Bonn (Germany, F.R.); Annual meeting on nuclear technology (JK '88); Jahrestagung Kerntechnik (JK '88); Luebeck-Travemuende (Germany, F.R.); 17-19 May 1988
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Short communication
Primary Subject
Source
Anon; 168 p; Feb 1993; p. 167; 7. international Beer Sheva seminar on MHD flows and turbulence; Jerusalem (Israel); 14-18 Feb 1993
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The testing stages in NET for the performance assessment of the various breeding blanket concepts developed at the present time in Europe for DEMO (LiPb and ceramic blankets) and the requirements upon NET to perform these tests are reviewed. Typical locations available in NET for blanket testing are the central outboard segments and the horizontal ports of in-vessel sectors. These test positions will be connectable with external test loops. The number of test loops (helium, water, liquid metal) will be such that each major class of blankets can be tested in NET. The test positions, the boundary conditions and the external test loops are identified and the requirements for test blankets are summarized (author). 6
Primary Subject
Source
Ingen, A.M. van; Nijsen-Vis, A. (Associatie Euratom-FOM, Nieuwegein (Netherlands). FOM-Instituut voor Plasmafysica); Klippel, H.T. (Netherlands Energy Research Foundation, Petten (Netherlands)) (eds.); 937 p; ISBN 0 444 87369 4;
; 1989; p. 115-123; North-Holland; Amsterdam (Netherlands); 15. Symposium on fusion technology; Utrecht (Netherlands); 19-23 Sep 1988

Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Published in summary form only
Original Title
Neuere Ueberlegungen zur konstruktiven Gestaltung der Abschirmblankets fuer NET
Primary Subject
Source
Deutsches Atomforum e.V., Bonn (Germany, F.R.); Kerntechnische Gesellschaft e.V., Bonn (Germany, F.R.); 789 p; May 1988; p. 687-690; INFORUM Verl; Bonn (Germany, F.R.); Annual meeting on nuclear technology (JK '88); Jahrestagung Kerntechnik (JK '88); Luebeck-Travemuende (Germany, F.R.); 17-19 May 1988
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Short communication. Nine breeder blanket concepts were studied by CFFTP to estimate blanket temperature profiles under similar operating conditions
Primary Subject
Record Type
Journal Article
Journal
CFFTP Journal; ISSN 0847-9437;
; v. 6(3); p. 1-2

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |