Published July 2007 | Version v1
Journal article

ITER: the 'path' to new energy source

  • 1. CEA Cadarache, Groupe de Surete et Environnement - Organisation ITER, 13 - Saint-Paul-lez-Durance (France)

Description

The purpose of the ITER reactor to be built at Cadarache will be to study combustion plasma physics in an experimental machine applying the fundamental principles of nuclear fusion technology in order to demonstrate the scientific and technical feasibility of fusion energy for peaceful purposes. The ITER international organisation, established under the terms of an agreement signed on 21 November 2006, will be responsible for the design, construction and operation of the ITER reactor. Design and operation were the subject of exhaustive studies to prove that this nuclear fusion reactor could meet safety and environmental protection objectives. The safety analysis has showed 2 main risk factors: the presence of tritium and the particulates produced in the plasma-wall interaction. At any moment of its running the ITER reactor is likely to contain a few kg of tritium. As for the particulates, they are going to pile up during ITER operation, ITER's design allows an accumulation of a few hundreds kg of carbon, beryllium and tungsten particulates in the toroid chamber. The main safety function, which is to prevent the release and dispersion of radio-toxic materials, is thus performed by two independent containment barriers. The first barrier is made up of the toroid vacuum chamber, the cooling system, the tritium processing system and the confinement systems of wastes. The second barrier involves hot cells, the containment building, and ventilation systems

Additional details

Additional titles

Original title (French)
ITER: la 'voie' vers une nouvelle source d'energie

Publishing Information

Journal Title
Controle (Paris)
Journal Issue
no.176
Journal Page Range
p. 100-107
ISSN
1254-8146
CODEN
CONTFB

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
38116417
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
DESIGN; ITER TOKAMAK; RISK ASSESSMENT; SAFETY; SAFETY ANALYSIS
Descriptors DEC
CLOSED PLASMA DEVICES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS