Tritium: Fuel of Fusion Reactors

Herausgegeben:Tanabe, Tetsuo

• Gebundenes Buch

Produktbeschreibung

This book focuses on tritium as a fuel for fusion reactors and a next-generation energy source. Following an introduction of tritium as a hydrogen radioisotope, important issues involved in establishing safe and economical tritium fuel cycles including breeding for a fusion reactor are summarized; these include the handling of large amounts of tritium: confinement, leakage, contamination, permeation, regulation and tritium accountancy, and impacts on surrounding areas. Targeting and encouraging the students and technicians who will design and operate fusion reactors in the near future, this book offers a valuable resource on tritium science and technology.

Produktdetails

• Verlag: Springer / Springer Japan / Springer, Berlin
• Artikelnr. des Verlages: 978-4-431-56458-4
• 1st ed. 2017
• Seitenzahl: 380
• Erscheinungstermin: 16. Dezember 2016
• Englisch
• Abmessung: 241mm x 160mm x 26mm
• Gewicht: 678g
• ISBN-13: 9784431564584
• ISBN-10: 4431564586
• Artikelnr.: 45506450

Autorenporträt

Inhaltsangabe

Introduction of a nuclear fusion reactor.- Characteristics of tritium.- Fuel flow and balance in a DT fusion reactor.- Burning plasma.- Behavior of fuels in reactor.- Tritium fueling system.- Tritium measurement I.- Tritium measurement II.- Permeation and Permeation Barrier.- Contamination and decontamination.- Isotope separation system (ISS).- Evaluation method of tritium breeding ratio using neutron transport equation.- Recovery of Tritium Bred in Blanket.- Safety confinement system.- Behavior of tritium released to the environment.

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Introduction of a nuclear fusion reactor.- Characteristics of tritium.- Fuel flow and balance in a DT fusion reactor.- Burning plasma.- Behavior of fuels in reactor.- Tritium fueling system.- Tritium measurement I.- Tritium measurement II.- Permeation and Permeation Barrier.- Contamination and decontamination.- Isotope separation system (ISS).- Evaluation method of tritium breeding ratio using neutron transport equation.- Recovery of Tritium Bred in Blanket.- Safety confinement system.- Behavior of tritium released to the environment.