Tritium Retention and Release Analysis for the U.S.-ITER Driver Blanket

Billone, M.C.; Chen, Lin; Attaya, H.; Gohar, Y.

doi:10.13182/fst91-a29469

Cited by 20 publications

(4 citation statements)

References 7 publications

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“…It was proposed that the inverted peaks were associated with the solubility of tritium in a surface layer that was decomposed or eliminated during conditioning. The inverted tritium recovery peaks in the 470 to 430°C temperature range correspond to a temperature range where LiOT or dissolved moisture is an important factor in determining the tritium inventory in Li20 (Billone et al 1991;Tetenbaum and Johnson 1984). Because the moisture levels in the BEATRIX-11 sweep gas are typically less than 0.1 Pa, the amount of moisture in the specimen is expected to remain below the LiOH solubility limit as the temperature is decreased.…”

Section: Inverted Recovery Peaksmentioning

confidence: 99%

BEATRIX-II, phase II: Data summary report

Slagle¹,

Hollenberg²

1996

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This report was prepared as an account of work sponsored by an agency of the United States Government Neither the United States Government nor any agency thereof, nor any of their employees, make any e t y , exprers or implied, or assums any legal liability or rrsponsiiility for the accuracy, completeness, or usefulness of any information, apparatus, pmduct, or process disdosed, AbstractThe BEATRIX-I1 experimental program was an International Energy Agency sponsored collaborative effort between Japan, Canada, and the United States to evaluate the performance of ceramic solid breeder materials in a fast-neutron environment at high burnup levels. This report addresses the Phase I1 activities, which included two in situ tritium-recovery canisters: temperaturechange and temperature-gradient. The temperatiire-change canister contained a Li20 ring specimen that had a nearly uniform temperature profile and was capable of temperature changes between 530 and 640°C. The temperature-gradient canister contained a LizZr03 pebble bed operating under a thermal gradient of 440 to 1100°C. Postirradiation examination was carried out to characterize the Phase 11 in situ specimens and a series of nonvented capsules designed to address the compatibility of beryllium with lithium-ceramic solid-breeder materials.The results of the BEATRIX-11, Phase 11, irradiation experiment provided an extensive data base on the in situ tritium-release characteristics of Li20 and Li2ZrOg for lithium burnups near 5%.The composition of the sweep gas was found to 'be a critical parameter in the recovery of tritium from both Li20 and Li2ZrO3. In general, increasing the amount of hydrogen in the sweep gas resulted in a transient tritium recovery peak indicative of a decrease in tritium inventory in the specimen. The ability of the Phase 11 temperature-change canister to vary temperature between 530 and 630°C indicated that increasing temperature resulted in. transient tritium-recovery peaks whose magnitude and duration were indicative of a relatively small tritium inventory in the Phase 11 Liz0 ring specimen at these temperatures. Throughout the Phase 1 1 irradiation, the centerline temperature of the Li2ZrOg specimen was nearly constant, inferring that the pebble bed remained physically the same throughout the irradiation.Tritium inventories measured during postirradiation examination confirmed that Li20 and . Li2ZrOg exhibited very low tritium retention during the Phase 11 irradiation. The tritium inventories .in Li2ZrOg after Phase 11 tended to be larger than those found for Li2ZrOg in other in situ experiments, but the larger values may reflect the larger generation rates in BEATRIX-II.A series of 20 capsules was irradiated to determine the compatibility of lithium ceraniics and beryllium under conditions similar to a fusion blanket. The lithium ceramics (Li20, Li2ZrO3, LiA102, and Li4SiO4) in contact with beryllium resulted in no observable chemical interaction for lithium burnups up to 4% and irradiation times up to 500 effective full-power days....

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Section: Inverted Recovery Peaksmentioning

confidence: 99%

BEATRIX-II, phase II: Data summary report

Slagle¹,

Hollenberg²

1996

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“…The 470-430°C temperature range associated with the major recovery peak during shutdown in helium is in the range where the LiOT or dissolved moisture is an important factor in determining the tritium inventory [14,151 in Li,O.…”

Section: This Behavior Is Verymentioning

confidence: 99%

In situ tritium from Li{sub 2}O and Li{sub 2}ZrO{sub 3} irradiated in a fast neutron flux: BEATRIX-II, Phase 1 and 2

Slagle¹,

Hollenberg

Kurasawa³

et al. 1994

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BEATRIX-I1 was an in situ tritium recovery experiment designed to characterize the behavior of lithium ceramics irradiated to high burnup in a fast neutron flux. This in situ tritium recovery experiment provided data on the performance of Li20 and Li,ZrO, under irradiation conditions covering a range of sweep gas compositions and temperatures. The experiment consisted o f two separate irradiation cycles which in turn included two vented tritium recovery canisters each. while Phase I1 operated for 203 EFPD of irradiation. resulted in lithium burnups in excess of 4%. Phase I operated for 300 Effective Full Power Days (EFPD) Both Phase I and I1 The tritium recovery behavior of Li,O and Li ZrO, was characterized using temperature transients, sweep gas composition changes and reactor power changes to effect changes in the tritium inventory. These parameter changes indicated that increasing temperatures or increasing concentrations of hydrogen in the sweep gas, in general, resulted in a decrease in the tritium inventories in the lithium ceramic. The results of these parameter changes allow comparison not only in the tritium recovery behaviors for Li,O versus Li,ZrO, but between different Li,O microstructures. The high neutron flux level in FFTF resulted in high tritium generation rates which combined with a responsive tritium measurement system allowed detailed observations on the tritium recovery behavior of Li,O and Li,ZrO,. During the course o f the experiment a number o f observations were made which did not appear consistent with a simplified view of the tritium recovery behavior of these materials. These observations included small negative tritium recovery peaks preceding the typical primary positive peaks; and, for specific temperature ranges, changes in tritium inventory which where opposite to the characteristic expected changes. extensive BEATRIX-I1 database o f tritium recovery results provides an opportunity for a better understanding of the tritium release behavior of these two candidates for a fusion solid breeder blanket. This anomalous behavior together with the (a) Pacific Northwest Laboratory is operated for the U. S. Department o f Energy by Battell e Memori a1 Institute under Contract DE-AC06-76RLO 1830,

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“…During irradiation,generatedtritium in a form of dissolved tritiated water could be present in LifO [11,12], and it is possible that this tritiatedwater could contributeto the surface morphologychanges. Type A surfaceswere found in specimenstending to have higher retained tritium inventoriessuch as the outer regions of the solid specimen.…”

Section: ¢ !mentioning

confidence: 99%