Published 1987 | Version v1
Book

Tritium removal from inert gases using Zr2Fe

  • 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--.