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Strategies of tritium extraction from neutron irradiated lithium aluminate

Abstract

Tritium (T) release peculiarities were examined for lithium aluminate ceramic breeder materials, prepared and selected in ENEA (Italian Agency for New Technology, Energy and the Environment) labs, both by post irradiation annealing and in-situ experiments. Different additives were added to the purging gas in order to improve T extraction and reduce T permeation through the stainless steel tubes. Preliminary results show that a sweeping gas mixture obtained by adding, to He, 100 vpm o water, can be as effective as Helium + 0.1 per cent hydrogen in extracting T, with a contemporary reduction of the permeation problems.
Publication Date:
Dec 31, 1990
Product Type:
Conference
Report Number:
ETDE-IT-93-51; CONF-8909101-2
Reference Number:
SCA: 700480; 700460; PA: ITAN-93:000139; SN: 93000947382
Resource Relation:
Conference: Workshop on tritium and advanced fuels in fusion reactors,Varenna (Italy),6-15 Sep 1989; Other Information: PBD: 1990
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; BREEDING PELLETS; TRITIUM RECOVERY; ITALIAN ENEA; ALUMINATES; LITHIUM COMPOUNDS; ADDITIVES; WATER; HYDROGEN; PERMEABILITY; HELIUM; 700480; 700460; COMPONENT DEVELOPMENT; MATERIALS STUDIES; HEATING AND FUELING SYSTEMS; FUELS
OSTI ID:
10130527
Research Organizations:
ENEA, Casaccia (Italy). Dipt. Tecnologie Intersettoriali di Base
Country of Origin:
Italy
Language:
English
Other Identifying Numbers:
Other: ON: DE93769396; TRN: 93:000139
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
ITAN
Size:
7 p.
Announcement Date:
Jul 04, 2005

Citation Formats

Carconi, P L, Casadio, S, Mancini, M R, Moauro, A, and Briec, M. Strategies of tritium extraction from neutron irradiated lithium aluminate. Italy: N. p., 1990. Web.
Carconi, P L, Casadio, S, Mancini, M R, Moauro, A, & Briec, M. Strategies of tritium extraction from neutron irradiated lithium aluminate. Italy.
Carconi, P L, Casadio, S, Mancini, M R, Moauro, A, and Briec, M. 1990. "Strategies of tritium extraction from neutron irradiated lithium aluminate." Italy.
@misc{etde_10130527,
title = {Strategies of tritium extraction from neutron irradiated lithium aluminate}
author = {Carconi, P L, Casadio, S, Mancini, M R, Moauro, A, and Briec, M}
abstractNote = {Tritium (T) release peculiarities were examined for lithium aluminate ceramic breeder materials, prepared and selected in ENEA (Italian Agency for New Technology, Energy and the Environment) labs, both by post irradiation annealing and in-situ experiments. Different additives were added to the purging gas in order to improve T extraction and reduce T permeation through the stainless steel tubes. Preliminary results show that a sweeping gas mixture obtained by adding, to He, 100 vpm o water, can be as effective as Helium + 0.1 per cent hydrogen in extracting T, with a contemporary reduction of the permeation problems.}
place = {Italy}
year = {1990}
month = {Dec}
}