Published September 1998 | Version v1
Journal article

Status of the ITER tritium plant design

  • 1. ITER, Naka, Ibaraki (Japan). Joint Central Team

Description

This paper provides an overview of the ITER tritium plant fuel cycle processes, followed by a description of the current design status of process, atmospheric detritiation, water detritiation, and tritium confinement systems. The evolution of process systems since the beginning of the engineering design activities (EDA) is emphasized. The ITER tritium plant provides high purity mixtures of tritium and deuterium to the fuelling systems for pellet injection, neutral beams, and gas puffing, and processes the plasma exhaust removed from the torus during pulsing and conditioning. Design of tritium-containing components, confinement systems, and air detritiation systems, to reduce tritium releases from routine effluents and accidents to very low levels is described. (orig.)

Additional details

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
39-40
Series
Part A
Journal Page Range
p. 875-882
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
4. international symposium on fusion nuclear technology (ISFNT-4)
Dates
6-11 Apr 1997
Place
Tokyo (Japan)

INIS

Country of Publication
Netherlands
Country of Input or Organization
Switzerland
INIS RN
29064558
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DEUTERIUM; THERMONUCLEAR FUELS; TOKAMAK DEVICES; TRITIUM
Descriptors DEC
BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; FUELS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; RADIOISOTOPES; STABLE ISOTOPES; THERMONUCLEAR DEVICES; YEARS LIVING RADIOISOTOPES

Optional Information

Notes
7 refs.