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Fusion technology 1996 : proceedings of the 19th Symposium on Fusion Technology, Lisbon, Portugal, 16-20 September 1996. Volume 1 /

The objective of these proceedings was to provide a platform for the exchange of information on the design, construction and operation of fusion experiments. The technology which is being developed for the next step devices and fusion reactors was also covered.

Detalles Bibliográficos
Clasificación:Libro Electrónico
Autores Corporativos: Symposium on Fusion Technology Lisbon, Portugal, Instituto Superior T�ecnico. Centro de Fus�ao Nuclear
Otros Autores: Varandas, C., Serra, F.
Formato: Electrónico Congresos, conferencias eBook
Idioma:Inglés
Publicado: Amsterdam ; New York : Elsevier, 1997.
Temas:
Acceso en línea:Texto completo

MARC

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111 2 |a Symposium on Fusion Technology  |n (19th :  |d 1996 :  |c Lisbon, Portugal) 
245 1 0 |a Fusion technology 1996 :  |b proceedings of the 19th Symposium on Fusion Technology, Lisbon, Portugal, 16-20 September 1996.  |n Volume 1 /  |c edited by C. Varandas and F. Serra. 
260 |a Amsterdam ;  |a New York :  |b Elsevier,  |c 1997. 
300 |a 1 online resource (1 volume) 
336 |a text  |b txt  |2 rdacontent 
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500 |a Papers. Described as proceedings. Also known as SOFT. 
520 |a The objective of these proceedings was to provide a platform for the exchange of information on the design, construction and operation of fusion experiments. The technology which is being developed for the next step devices and fusion reactors was also covered. 
588 0 |a Print version record. 
505 0 |a Front Cover; Fusion Technology 1996; Copyright Page; PREFACE; COMMITTEE MEMBERS; INDUSTRIAL EXHIBITORS; Table of Contents; PART I: INVITED TALKS; Chapter 1. Nuclear fusion, an energy source; Abstract; 1. Introduction; 2. Is energy an issue today?; 3. How can future energy be met?; 4. How can fusion contribute to future energy supply?; 5. How and when is fusion going to demonstrate its potential as an energy source?; 6. Conclusions; References; Chapter 2. ITER overview; Abstract; 1. Introduction; 2. Current overall status of the activities; 3. Physics and engineering requirements. 
505 8 |a 4. ITER design5. Fusion technology R & D for ITER; 6. Conclusion; Acknowledgements; References; Chapter 3. The ITER magnet system; Abstract; 1. Introduction; 2. Description of the mechanical design; 3. TF coils design description; 4. Central solenoid (reference design); 5. PF coil system design and maintenance considerations; 6. Correction coils; 7. Conductor; 8. ITER magnet R & D programme; 9. Summary of ITER plasma control; 10. Alternate central solenoid design; 11. Conclusions; Acknowledgements; References; Chapter 4. Design of in-vessel components for ITER; Abstract; 1. Introduction. 
505 8 |a 2. Blanket3. Divertor; 4. Vacuum vessel; 5. Conclusions; Acknowledgements; References; Chapter 5. Management of waste from the International Thermonuclear Experimental Reactor and from future fusion power plants; Abstract; 1. Introduction; 2. Use of low-activation materials; 3. Detritiation; 4. Interim storage; 5. Recycling and clearance; 6. Volume reduction; 7. Packaging; 8. Waste disposal; 9. Chemically toxic waste; 10. Conclusions; References; Chapter 6. Status of the European breeding blanket technology; Abstract; 1. Introduction; 2. Description of the breeder blanket concepts for DEMO. 
505 8 |a 3. Review of the major R & D activities4. Specific activities related to ITER test blanket modules; 5. Conclusions; References; Chapter 7. Recent results on vacuum pumping and fuel clean-up; Abstract; 1. Introduction; 2. Plasma exhaust streams; 3. Recent experimental and technological developments in the fields of pumping and fuel clean-up; 4. Conclusions; References; Chapter 8. Remote handling on fusion experiments; 1. Introduction; 2. Remote handling requirements and constraints; 3. A remote handling application from JET; 4. Conclusions; Acknowledgements; References. 
505 8 |a Chapter 9. Possible divertor solutions for a fusion reactor. Part I. Physical aspects based on present day divertor operation 1Abstract; 1. Introduction; 2. Variations of the divertor configuration; 3. Optimization criteria for radiative H-mode operation; 4. Optimum radiating species for ITER conditions; 5. Conclusions; References; Chapter 10. Possible divertor solutions for a fusion reactor. Part 2. Technical aspects of a possible divertor; Abstract; 1. Introduction; 2. Heat sink; 3. Plasma facing materials; 4. Attachment of the plasma facing material to the heat sink. 
650 0 |a Nuclear fusion  |v Congresses. 
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655 7 |a Conference papers and proceedings  |2 fast  |0 (OCoLC)fst01423772 
655 7 |a Conference papers and proceedings.  |2 lcgft 
655 7 |a Actes de congr�es.  |2 rvmgf  |0 (CaQQLa)RVMGF-000001049 
700 1 |a Varandas, C. 
700 1 |a Serra, F. 
710 2 |a Instituto Superior T�ecnico.  |b Centro de Fus�ao Nuclear. 
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856 4 0 |u https://sciencedirect.uam.elogim.com/science/book/9780444827623  |z Texto completo