Design and operational experience with a portable tritium cleanup system
Abstract
The authors built a portable tritium cleanup system to scavenge tritium from contaminated gases in any tritium-containing system in the LLNL Tritium Facility. The cleanup system uses standard catalytic oxidation of tritium to water followed by water removal with a molecular sieve dryer. The cleanup unit, complete with instrumentation, is contained in a portable cart that is rolled into place and connected to the apparatus to be cleaned. The cleanup system is effective, low-tech, simple, and reliable. The nominal flow rate of the system is 30 liters/minute, and the decontamination factor is {gt}1000. In this paper the authors will show design information on their portable cleanup system, and will discuss operational experience with it over the past several years.
- Authors:
-
- Lawrence Livermore National Lab., CA (United States)
- Publication Date:
- OSTI Identifier:
- 5154393
- Report Number(s):
- CONF-910920-
Journal ID: ISSN 0748-1896; CODEN: FUSTE
- Resource Type:
- Conference
- Journal Name:
- Fusion Technology; (United States)
- Additional Journal Information:
- Journal Volume: 21:2; Conference: 4. topical meeting on tritium technology in fission, fusion, and isotopic applications, Albuquerque, NM (United States), 29 Sep - 4 Oct 1991; Journal ID: ISSN 0748-1896
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; PORTABLE EQUIPMENT; DESIGN; TRITIUM; SCAVENGING; CATALYSIS; CONTAMINATION; DECONTAMINATION; FLOW RATE; GASES; LAWRENCE LIVERMORE LABORATORY; MOLECULAR SIEVES; OPERATION; OXIDATION; REMOVAL; TRITIUM COMPOUNDS; WATER; ADSORBENTS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CHEMICAL REACTIONS; CLEANING; EQUIPMENT; FLUIDS; HYDROGEN COMPOUNDS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NATIONAL ORGANIZATIONS; NUCLEI; ODD-EVEN NUCLEI; OXYGEN COMPOUNDS; RADIOISOTOPES; US AEC; US DOE; US ERDA; US ORGANIZATIONS; YEARS LIVING RADIOISOTOPES; 052001* - Nuclear Fuels- Waste Processing
Citation Formats
Maienschein, J L, Wilson, S W, and Garcia, F. Design and operational experience with a portable tritium cleanup system. United States: N. p., 1992.
Web.
Maienschein, J L, Wilson, S W, & Garcia, F. Design and operational experience with a portable tritium cleanup system. United States.
Maienschein, J L, Wilson, S W, and Garcia, F. 1992.
"Design and operational experience with a portable tritium cleanup system". United States.
@article{osti_5154393,
title = {Design and operational experience with a portable tritium cleanup system},
author = {Maienschein, J L and Wilson, S W and Garcia, F},
abstractNote = {The authors built a portable tritium cleanup system to scavenge tritium from contaminated gases in any tritium-containing system in the LLNL Tritium Facility. The cleanup system uses standard catalytic oxidation of tritium to water followed by water removal with a molecular sieve dryer. The cleanup unit, complete with instrumentation, is contained in a portable cart that is rolled into place and connected to the apparatus to be cleaned. The cleanup system is effective, low-tech, simple, and reliable. The nominal flow rate of the system is 30 liters/minute, and the decontamination factor is {gt}1000. In this paper the authors will show design information on their portable cleanup system, and will discuss operational experience with it over the past several years.},
doi = {},
url = {https://www.osti.gov/biblio/5154393},
journal = {Fusion Technology; (United States)},
issn = {0748-1896},
number = ,
volume = 21:2,
place = {United States},
year = {Sun Mar 01 00:00:00 EST 1992},
month = {Sun Mar 01 00:00:00 EST 1992}
}