Design and evaluation of gaseous tritium recovery system using commercially available membrane type dehumidifier
- 1. National Institute for Fusion Science, Department of Helical Plasma Research, Toki, Gifu (Japan)
Description
In order to realize the planned deuterium plasma experiments using the Large Helical Device, the National Institute for Fusion Science (NIFS) is planning to install a system for tritium recovery from exhaust gas. While adopting typical tritium recovery systems, NIFS has also made plans for the development of a compact reduced-waste recovery system by applying a membrane type dehumidifier. A commercially available membrane dehumidifier was evaluated experimentally for this purpose with the results indicating that such a membrane is feasible for practical application. A small-scale test apparatus having a capacity 1/10 (30 m3(NTP)/h) that of the actual tritium recovery system with the same flow control system was evaluated under actual operating conditions, and the necessary performance for design and operation of the actual system was elucidated. (author)
Availability note (English)
Available from http://dx.doi.org/10.1080/00223131.2012.723177Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 49
- Journal Issue
- 9-10
- Journal Page Range
- p. 1018-1027
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 44050072
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- DESIGN; DEUTERIUM; EVALUATION; FILTERS; ISOTOPE SEPARATION; LHD DEVICE; MEMBRANES; PLASMA; POLYMERS; TRITIUM RECOVERY
- Descriptors DEC
- CLOSED PLASMA DEVICES; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NUCLEI; ODD-ODD NUCLEI; SEPARATION PROCESSES; STABLE ISOTOPES; THERMONUCLEAR DEVICES
Optional Information
- Notes
- 13 refs., 13 figs., 4 tabs.