Last edited by Vijin
Friday, July 31, 2020 | History

2 edition of Tritium systems concepts for the next European torus found in the catalog.

Tritium systems concepts for the next European torus

S. K. Sood

Tritium systems concepts for the next European torus

by S. K. Sood

  • 54 Want to read
  • 26 Currently reading

Published by Canadian Fusion Fuels Technology Project in Mississauga, Ont .
Written in English

    Subjects:
  • Fusion reactors -- Safety measures,
  • Tritium -- Recovery

  • Edition Notes

    Statementprincipal authors S.K. Sood, O.K. Kventon, contributors: A.H. Dombra ... [et al.].
    SeriesReport / Canadian Fusion Fuels Technology Project -- G-86020, Report (Canadian Fusion Fuels Technology Project) -- G-86020
    ContributionsKventon, O. K., Canadian Fusion Fuels Technology Project.
    Classifications
    LC ClassificationsTK9204 S6 1986
    The Physical Object
    Pagination159 p. :
    Number of Pages159
    ID Numbers
    Open LibraryOL16645055M

    @article{osti_, title = {Radiolysis aspects of the aqueous self-cooled blanket concept and the problem of tritium extraction}, author = {Bruggeman, A. and Snykers, M. and DeRegge, P. and Embrechts, M.J.}, abstractNote = {In the Aqueous Self-Cooled Blanket (ASCB) concept, an aqueous /sup 6/Li solution in a metallic structure is used as a fusion reactor shielding-breeding blanket.   • first steps of year plan • prove / disprove fusion feasibility for commercialisation • > $10 Billion machine • > GJ of stored magnetic energy • MW of fusion for seconds vs state-of-the-art: 16MW of fusion for 1 second (Joint European Torus) Tritium – Deuterium Fusion Deuterium Tritium Neutron Helium + → + + Energy.

      The activity began in with the study of the Joint European Torus vacuum and active gas handling systems. Two years later the neutral beam injectors and the power supply systems were considered. This year the ion cyclotron resonant heating system is under evaluation. Tritium virtually does not exist in nature (it has a half-life of years). So the success relies on breeding the tritium inside the reactor. One of the missions for the later stages of ITER operation is to demonstrate the feasibility of one or more concepts of tritium production through the so-called “Test Blanket Module” (TBM) program.

    Future work will include broadening the scope of the code, particularly in the area of materials selection, to more accurately simulate tokamak configurations such as the Next European Torus (NET) and the Fusion Engineering Reactor (FER). 18 refs., 2 figs.,more» «less. This model, which has been applied to phase 2A of the International Tokamak Reactor/Next European Torus project, is used to predict the effect of the operating conditions of the blanket, as well as those of a spray tower employed as a tritium recovery unit, and the kinetic parameters for the permeation and desorption processes.


Share this book
You might also like
Contemporary Caribbean

Contemporary Caribbean

Policy studies on taxation

Policy studies on taxation

Southeast Asian Transitions

Southeast Asian Transitions

Studies in consumer demand.

Studies in consumer demand.

Optimization of induction motor efficiency, Volume 2

Optimization of induction motor efficiency, Volume 2

Love war stories

Love war stories

Hic et ubique

Hic et ubique

Intentional teaching

Intentional teaching

Bad Death of Eduard Delacroix #4

Bad Death of Eduard Delacroix #4

INI115 LONEDALE OPERATOR CIRC VHS

INI115 LONEDALE OPERATOR CIRC VHS

Black Panther Fire Salvage EIS, Klamath National Forest

Black Panther Fire Salvage EIS, Klamath National Forest

Education in a university

Education in a university

Practical scientific Russian

Practical scientific Russian

James Watt (1736-1819)

James Watt (1736-1819)

Tritium systems concepts for the next European torus by S. K. Sood Download PDF EPUB FB2

These elements form part of the reference concept intended to identify research and development priorities for the European Fusion Technology program, and provide a framework for the further definition of the NET design. With the exception of the vacuum train, the engineering concepts of process elements described are relatively straightforward.

Nuclear Engineering and Design/Fusion 3 () North-Holland, Amsterdam THE NEXT EUROPEAN TORUS Romano TOSCHI The NET Team, c/o Max-Planck-lnstitut ff~r Plasmaphysik, Boltzmannstrasse 2, D Garching bei MDnchen, Fed.

Rep. Germany Received August The Next European Torus (NET) is the major plasma device envisaged, in the European Cited by:   The main elements of the tritium handling system for a machine such as NET have already [1, 2, 3] been outlined and several requirements (actual data not yet well fixed but giving an order of magnitude) will be mentioned later Difficulties in connection with processes.

The primary function of the processing system is to assure a total DT plasma exhaust purification efficiency (Cited by: 4. Richard Kembleton, in Managing Global Warming, Status of current research. The current largest tokamak and only magnetic device still operating, which has burnt D-T is JET, the Joint European Torus, located at Culham Centre for Fusion Energy, Oxfordshire, United is the world's most powerful tokamak and is the focal point of the European fusion research program.

Because of a large tritium experience in the Bruyeres-le-Chatel Research Center (Atomic Energy Commission-FRANCE), new activities could be undertaken in inside the European Fusion Technology Program, especially tritium studies within the frame work of the Next European Torus.

After presenting the general tritium research program which Cited by: 4. The dimensioning of the permeator considered a tritium extraction efficiency of 80%. An exhaustive investigation on the vacuum system needed for the PAV is also presented.

The choice of the most promising vacuum systems took into account the reliability and tritium compatibility of both high and rough pumps. The book introduces the major science and technology issues for magnetic fusion energy systems, and explores the progress in the field by examining the contributions to fusion understanding from experimental machines, both leading up to the ITER era, and continuing as.

Abstract. This paper summarizes Fuel Cycle options with emphasis on recent innovations to reduce tritium irwentory. Tritium system design concepts described in the NET Pre-design Report [Toschi et al, ], and ITER-CDA Fuel Cycle Design Report [Leger et al., ] are supplemented by designs which address the high-throughput requirements currently under discussion for ITER (EDA) and reactors.

The paper describes the progress of the studies on first wall and liquid breeder blankets for tritium production in the Next European Torus (NET). Two concepts of first wall/blanket segments are described, using 17Li83Pb as breeder and water as coolant.

In this article, the methodology was updated and tritium and DTS for DEMO design were estimated. Moreover, the tritium and dust release pathways were highlighted according to different accidental scenarios. These results were obtained for all blanket concepts, which are analyzing in the ongoing DEMO EUROFusion project.

Various blanket concepts with different neutronic characteristics are taken into account: a helium-cooled solid breeder blanket with beryllium as neutron multiplier, a self-cooled liquid-metal blanket with the eutectic alloy PbLi, or, alternatively, pure lithium as breeding material/coolant and an aqueous lithium salt solution blanket.

ITER (originally the International Thermonuclear Experimental Reactor) is an international nuclear fusion research and engineering megaproject, which will be the world's largest magnetic confinement plasma physics experiment. It is an experimental tokamak nuclear fusion reactor that is being built next to the Cadarache facility in Saint-Paul-lès-Durance, in Provence, southern France.

Next European Torus In-Vessel Components. Max Chazalon, Jean-Louis Boutard, Michael Ian Budd, Antonino Cardella, Wolfgang Dänner, Paul Dinner, Dain Evans, Markus Iseli, Bernard Libin, Frans Moons, Jos Nihoul, Marc A.

Vassiliadis, Gottfried Vieider, Chung Hsiung Wu, Ezio Zolti. Tritium fuel has been successfully used in the Tokamak Fusion Test Reactor (TFTR) and the Joint European Torus (JET) producing 10 and 16 MW of fusion power respectively[1, 2].

This experience together with focussed laboratory studies, has illuminated the challenges. Technologie budoucnosti. Využívám nejmodernější technologie, díky kterým dokážeme nabídnout špičkový výkon a jedinečné funkcionality.

However, recent R&D on pumping concepts for the European DEMO torus vacuum vessel has shown that diffusion pump could be also useful for PAV purposes due to the absence of moving parts, compatibility with tritium and good pumping speed for light molecules [35, 36].

Explore the latest full-text research PDFs, articles, conference papers, preprints and more on FIELD BOTANY. Find methods information, sources, references or conduct a literature review on FIELD. @article{osti_, title = {Tritium production from ceramic targets: a summary of the Hanford Coproduct Program}, author = {Johnson, Jr, A B and Kabele, T J and Gurwell, W E}, abstractNote = {Early-generation fusion reactors will require tritium breeding from lithium or lithium compounds.

Some current fusion reactor conceptual designs specify ceramic lithium compounds (lithium aluminate. The presence of tritium in tokamaks is a key issue associated with the materials that are most likely to be used for the type of equipment in the plant and for tritiated waste management.

K.M. Kalyanam's 28 research works with citations and 1, reads, including: A COMPACT, LOW COST, TRITIUM REMOVAL PLANT FOR CANDU-6 REACTORS. W. Obert's 43 research works with 1, citations and 1, reads, including: JET experiments with keV 3He and 4He neutral beam injection and neutron diagnostic applications.JET, the Joint European Torus, is the world's largest operational magnetically confined plasma physics experiment, located at Culham Centre for Fusion Energy in Oxfordshire, on a tokamak design, the fusion research facility is a joint European project with a main purpose of opening the way to future nuclear fusion grid energy.

JET was one of a number of tokamak reactors built in the.An overview is given of the tritium technology activities carried out in the European national laboratories associated with the European Fusion Programme and in the European Joint Research Center.

The relationship of these activities to the Next European Torus (NET) design priorities is discussed, and the current status of the research is.