Published 1987
| Version v1
Book
Tritium removal from inert gases using Zr2Fe
Creators
- 1. Los Alamos National Lab., Tritium Systems Test Assembly, Los Alamos, NM (USA)
Description
Tritium handling invariably requires multiple containment to ensure personnel safety and to control emissions to the environment. For this measure to be effective, tritiated environments require periodic or continuous tritium removal. Presently this is achieved by oxidizing tritium bearing compounds followed by adsorption of tritiated water on molecular sieves. An experimental program was initiated to examine the potential of a metal getter detritiation process. In particular the tritium removal characteristics of a zirconium-alloy, Zr2Fe, were studied
Additional details
Publishing Information
- Publisher
- IEEE Service Center.
- Imprint Place
- Piscataway, NJ (USA)
- Imprint Title
- Proceedings of the 12th symposium on fusion engineering
- Imprint Pagination
- vp.
- Journal Page Range
- p. 1239-1242.
Conference
- Title
- 12. symposium on fusion engineering.
- Dates
- 12-16 Oct 1987.
- Place
- Monterey, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21021721
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- GETTERING; INERT ATMOSPHERE; IRON ALLOYS; SEPARATION PROCESSES; THERMONUCLEAR DEVICES; TRITIUM; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOYS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CONTROLLED ATMOSPHERES; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- CONF-871007--.