Chemical form of released tritium from solid breeder materials under the various purge gas conditions
- 1. Graduate School of Engineering Science, Kyushu University, Fukuoka 812-8581 (Japan)
- 2. Tokai Establishment, JAEA, Ibaraki 319-1195 (Japan)
- 3. Naka Establishment, JAEA, Ibaraki 319-1195 (Japan)
Description
Understanding of the release behavior of bred tritium from solid breeder materials is necessary to design tritium recovery system from blanket of a fusion reactor because permeation loss of bred tritium in the piping system or type of tritium recovery system depends on the tritium release behavior. It has been reported by the present authors that behavior of tritium release from solid breeder grain is consisted of diffusion in grain, tritium transfer at surface layer and surface reactions on grain surface such as adsorption or isotope exchange reactions. Chemical form of released tritium from Li4SiO4 (from FzK), LiAlO2 (from JAERI), Li2TiO3 (from CEA) and Li2ZrO3 (from MAPI) under various purge gas condition is discussed in this study by using the data obtained from the out-of-pile tritium release experiment in JAEA and fitting results estimated by the tritium release model formed by the present authors. And then the tritium release behavior and chemical form of tritium in the test blanket module with solid breeder under the ITER condition is also discussed based on the estimation obtained using the tritium release model
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2007.07.002Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2007.07.002;
- PII
- S0920-3796(07)00345-6;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 82
- Journal Issue
- 15-24
- Journal Page Range
- p. 2147-2151
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 24. symposium on fusion technology
- Acronym
- SOFT-24
- Dates
- 11-15 Sep 2006
- Place
- Warsaw (Poland)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39068495
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADSORPTION; DESIGN; DIFFUSION; ISOTOPIC EXCHANGE; ITER TOKAMAK; LAYERS; LITHIUM SILICATES; LITHIUM TITANATES; LOSSES; SURFACES; TRITIUM; TRITIUM RECOVERY
- Descriptors DEC
- ALKALI METAL COMPOUNDS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; LITHIUM COMPOUNDS; NUCLEI; ODD-EVEN NUCLEI; OXYGEN COMPOUNDS; RADIOISOTOPES; SILICATES; SILICON COMPOUNDS; SORPTION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TITANATES; TITANIUM COMPOUNDS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT COMPOUNDS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.