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Tritium release from EXOTIC-7 orthosilicate pebbles. Effect of burnup and contact with beryllium during irradiation

Abstract

EXOTIC-7 was the first in-pile test with {sup 6}Li-enriched (50%) lithium orthosilicate (Li{sub 4}SiO{sub 4}) pebbles and with DEMO representative Li-burnup. Post irradiation examinations of the Li{sub 4}SiO{sub 4} have been performed at the Forschungszentrum Karlsruhe (FZK), mainly to investigate the tritium release kinetics as well as the effect of Li-burnup and/or contact with beryllium during irradiation. The release rate of Li{sub 4}SiO{sub 4} from pure Li{sub 4}SiO{sub 4} bed of capsule 28.1-1 is characterized by a broad main peak at about 400degC and by a smaller peak at about 800degC, and that from the mixed beds of capsule 28.2 and 26.2-1 shows again these two peaks, but most of the tritium is now released from the 800degC peak. This shift of release from low to high temperature may be due to the higher Li-burnup and/or due to contact with Be during irradiation. Due to the very difficult interpretation of the in-situ tritium release data, residence times have been estimated on the basis of the out-of-pile tests. The residence time for Li{sub 4}SiO{sub 4} from caps. 28.1-1 irradiated at 10% Li-burnup agrees quite well with that of the same material irradiated at Li-burnup lower than 3% in the EXOTIC-6 experiment.  More>>
Authors:
Scaffidi-Argentina, F; Werle, H [1] 
  1. Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reaktortechnik
Publication Date:
Mar 01, 1998
Product Type:
Conference
Report Number:
JAERI-Conf-98-006; CONF-9710221-
Reference Number:
SCA: 700480; 360206; PA: JPN-98:007186; EDB-99:018033; SN: 98001997777
Resource Relation:
Conference: 6. international workshop on ceramic breeder blanket interactions, Mito (Japan), 22-24 Oct 1997; Other Information: PBD: Mar 1998; Related Information: Is Part Of Proceedings of the sixth international workshop on ceramic breeder blanket interactions; Noda, Kenji [ed.]; PB: 296 p.
Subject:
70 PLASMA PHYSICS AND FUSION; 36 MATERIALS SCIENCE; THERMONUCLEAR REACTOR MATERIALS; BREEDING BLANKETS; LITHIUM SILICATES; BREEDING PELLETS; POST-IRRADIATION EXAMINATION; HFR REACTOR; TRITIUM RECOVERY; TEMPERATURE DEPENDENCE; BERYLLIUM; INTERACTIONS
OSTI ID:
300374
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE98755721; TRN: JP9807186
Availability:
OSTI as DE98755721
Submitting Site:
JPN
Size:
pp. 161-169
Announcement Date:
Feb 01, 1999

Citation Formats

Scaffidi-Argentina, F, and Werle, H. Tritium release from EXOTIC-7 orthosilicate pebbles. Effect of burnup and contact with beryllium during irradiation. Japan: N. p., 1998. Web.
Scaffidi-Argentina, F, & Werle, H. Tritium release from EXOTIC-7 orthosilicate pebbles. Effect of burnup and contact with beryllium during irradiation. Japan.
Scaffidi-Argentina, F, and Werle, H. 1998. "Tritium release from EXOTIC-7 orthosilicate pebbles. Effect of burnup and contact with beryllium during irradiation." Japan.
@misc{etde_300374,
title = {Tritium release from EXOTIC-7 orthosilicate pebbles. Effect of burnup and contact with beryllium during irradiation}
author = {Scaffidi-Argentina, F, and Werle, H}
abstractNote = {EXOTIC-7 was the first in-pile test with {sup 6}Li-enriched (50%) lithium orthosilicate (Li{sub 4}SiO{sub 4}) pebbles and with DEMO representative Li-burnup. Post irradiation examinations of the Li{sub 4}SiO{sub 4} have been performed at the Forschungszentrum Karlsruhe (FZK), mainly to investigate the tritium release kinetics as well as the effect of Li-burnup and/or contact with beryllium during irradiation. The release rate of Li{sub 4}SiO{sub 4} from pure Li{sub 4}SiO{sub 4} bed of capsule 28.1-1 is characterized by a broad main peak at about 400degC and by a smaller peak at about 800degC, and that from the mixed beds of capsule 28.2 and 26.2-1 shows again these two peaks, but most of the tritium is now released from the 800degC peak. This shift of release from low to high temperature may be due to the higher Li-burnup and/or due to contact with Be during irradiation. Due to the very difficult interpretation of the in-situ tritium release data, residence times have been estimated on the basis of the out-of-pile tests. The residence time for Li{sub 4}SiO{sub 4} from caps. 28.1-1 irradiated at 10% Li-burnup agrees quite well with that of the same material irradiated at Li-burnup lower than 3% in the EXOTIC-6 experiment. In spite of the observed shift in the release peaks from low to high temperature, also the residence time for Li{sub 4}SiO{sub 4} from caps. 26.2-1 irradiated at 13% Li-burnup agrees quite well with the data from EXOTIC-6 experiment. On the other hand, the residence time for Li{sub 4}SiO{sub 4} from caps. 28.2 (Li-burnup 18%) is about a factor 1.7-3.8 higher than that for caps. 26.2-1. Based on these data on can conclude that up to 13% Li-burnup neither the contact with beryllium nor the Li-burnup have a detrimental effect on the tritium release of Li{sub 4}SiO{sub 4} pebbles, but at 18% Li-burnup the residence time is increased by about a factor three. (J.P.N.)}
place = {Japan}
year = {1998}
month = {Mar}
}