Safety in tritium handling technology
Author(s)
Bibliographic Information
Safety in tritium handling technology
(Euro courses, Nuclear science and technology ; v. 1)
Kluwer Academic, c1993
Available at 4 libraries
  Aomori
  Iwate
  Miyagi
  Akita
  Yamagata
  Fukushima
  Ibaraki
  Tochigi
  Gunma
  Saitama
  Chiba
  Tokyo
  Kanagawa
  Niigata
  Toyama
  Ishikawa
  Fukui
  Yamanashi
  Nagano
  Gifu
  Shizuoka
  Aichi
  Mie
  Shiga
  Kyoto
  Osaka
  Hyogo
  Nara
  Wakayama
  Tottori
  Shimane
  Okayama
  Hiroshima
  Yamaguchi
  Tokushima
  Kagawa
  Ehime
  Kochi
  Fukuoka
  Saga
  Nagasaki
  Kumamoto
  Oita
  Miyazaki
  Kagoshima
  Okinawa
  Korea
  China
  Thailand
  United Kingdom
  Germany
  Switzerland
  France
  Belgium
  Netherlands
  Sweden
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  United States of America
Note
"Based on the lectures given during the Eurocourse ... held at the Joint Research Centre, Ispra, Italy, April 28-30, 1993"--T.p. verso
"For the Commission of the European Communities"--Cover
Includes bibliographical references
Description and Table of Contents
Description
The use of tritium as a basic fuel material in a thermonuclear fusion reactor raises particular safety issues due to the combined effects of its physico chemical properties and radioactive nature. Furthermore the possibility of attaining further significant progresses in developing and demonstrating the feasibility of tritium burning devices relies on the handling of tritium macroquantities, say ten grammes, in a safe and reliable manner. It is also undoubted that, apart from technological constraints, any validation and exploitation of thermonuclear fusion as a source of energy will be strongly conditioned by the application of stringent operational and environmental safety criteria as it derives from norms of the modern legislation and public acceptance considerations. Even if the safe handling of tritium has already been demonstrated to be feasible on a full fuel cycle scale, it is unanimously recognized that further efforts are still to be concentrated on the improvement of current concepts and development of advanced technologies. Some of the areas requiring substantial additional efforts are plasma exhaust fuel c1ean-up, tritium pellet injection, processing of inert carrier gas, development of large free-oil pumps,tritlUm process analytics, development of large detritiation systems, beryllium-tritium interaction studies, tritium hold-up studies in getter beds, adsorbers and structural materials, tritium recovery from first wall, structural and breeder materials for minimizing tritiated waste arising,tritium storage technology, tritiated waste disposal technolo~y, methodology for routine tritium accountancy,etc . . Most of them are intrinsically related to the safety requirement of tritium technology.
Table of Contents
- Preface. 1. Fundamentals on Tritium
- H. Dworschak. 2. Tritium Processing Using Scavenger Beds: Theory and Operation
- W.T. Shmayda. 3. Tritium Handling Options: from NET to Power Reactor
- P.J. Dinner, D.K. Murdoch. 4. Tritium Materials Interactions
- N.P. Kherani, W.T. Shmayda. 5. Tritium Storage
- R.-D. Penzhorn. 6. Tritium Containment
- J.M. Miller. 7. Radiation Protection - Tritium Instrumentation and Monitoring Methods
- E. Dodi, A. Benco. 8. Tritium Biological Hazard and Dosimetry
- J. Piechowski. 9. Radiological Protection and Environmental Safety
- A.A. Cigna, L. Risposi. 10. Dismantling of Tritiated Facilities Management of Tritiated Wastes
- P. Giroux. 11. JET Tritium Experience
- A.C. Bell, JET Team. Index.
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