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.