Postirradiation examination of BEATRIX-II, phase I

Slagle, O.D.; Takahashi, Tadashi; Hobbs, F.D.; Noda, K.; Baldwin, David L.; Hollenberg, G.W.; Verrall, R.A.

doi:10.1016/0022-3115(94)90982-2

Cited by 9 publications

(7 citation statements)

References 7 publications

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“…In spite of these extreme conditions, Li20 and Li2Zr03 performed very well; Li20 exhibited good tritium release throughout the irradiation, and this was confirmed by a measured vety low tritium inventory [34]. Ceramic integrity was maintained during irradiation (burnup 5Yo), although some structure changes and swelling occurred along with a very small loss of lithium [34,35].…”

Section: Irradiation Performance -Laboratory and [N-reactor Testsmentioning

confidence: 84%

“…Ceramic integrity was maintained during irradiation (burnup 5Yo), although some structure changes and swelling occurred along with a very small loss of lithium [34,35]. For Li2Zr03 at this burnup level, tritium release was constant, with no indication that second phase formation degrades tritium release behavior.…”

Section: Irradiation Performance -Laboratory and [N-reactor Testsmentioning

confidence: 93%

See 1 more Smart Citation

Ceramic breeder materials: Status and needs

Johnson

Noda

Roux

1998

Journal of Nuclear Materials

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100

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Section: Irradiation Performance -Laboratory and [N-reactor Testsmentioning

confidence: 84%

Section: Irradiation Performance -Laboratory and [N-reactor Testsmentioning

confidence: 93%

Ceramic breeder materials: Status and needs

Johnson

Noda

Roux

1998

Journal of Nuclear Materials

Self Cite

100

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“…However, the tritium recovery rate of 1,000 ppmH 2 became the same as the value at 10,000 ppmH 2 after about 5 h from changing the hydrogen content. In the BEATRIX-II, [7][8][9] increasing the hydrogen content in sweep gas resulted in a transient tritium recovery peak which indicated a decrease in tritium inventory in the specimen. Decreasing hydrogen concentration from the reference sweep gas (1,000 ppmH 2 ) resulted in an increase in the tritium inventory.…”

Section: Irradiation Test With Multi-layered Pebble-bed Mockupmentioning

confidence: 99%

“…The major advantage of in-situ irradiation experiments is the capability to provide a neutron flux over a large volume prior to the availability of a fusion reactor. As the recent insitu irradiation tests, CRITIC-III (Canada), 6) BEATRIX-II (US/Japan/Canada), [7][8][9] EXOTIC (Netherlands/EU) [10][11][12] and others were conducted. However, these experiments used relatively small amount of specimen for characterization of tritium breeders and the structures of a fusion blanket have not been simulated.…”

Section: Introductionmentioning

confidence: 99%

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li₂TiO₃Pebble Bed in Japan

Tsuchiya¹,

Nakamichi²,

Nagao³

et al. 2001

Journal of Nuclear Science and Technology

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Lithium titanate (Li 2 TiO 3 ) is one of the most attractive tritium breeders for breeding blanket in fusion reactor from view points of low tritium inventory, high chemical stability and so on. The data on the performance of a blanket mockup with pebble bed under neutron irradiation is needed for the design of breeding blanket. To obtain such data, two kinds of the blanket in-pile mockups with Li 2 TiO 3 pebble bed were developed and the in-situ tritium recovery experiments were carried out in the Japan Materials Testing Reactor (JMTR). In these studies, effects of various parameters, i.e., irradiation temperature, sweep gas flow rate, etc., on the tritium recovery behavior from Li 2 TiO 3 pebble bed were evaluated. It was found that the tritium recovery (R) to tritium generation (G) ratio (R/G) increased with increasing the temperature of Li 2 TiO 3 pebble bed and was saturated when the temperature of Li 2 TiO 3 pebble bed at the outside edge exceeded 300 • C. Additionally, the sweep gas flow rate in the range of 100 to 900 cm 3 /min affected very little the tritium recovery from Li 2 TiO 3 pebble bed. A good prospect for the design of breeding blankets using Li 2 TiO 3 pebble bed was obtained from these results of in-situ experiments.

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“…The major advantage of in situ irradiation experiments is its capability to provide such information with respect to neutron flux over a large volume prior to availability of a fusion reactor. Up to now, in situ irradiation tests such as CRITIC-III (Canada) [1], BEATRIX-II (US/ Japan/Canada) [2][3][4], EXOTIC (Netherlands/EU) [5][6][7] and others were conducted.…”

Section: Introductionmentioning

confidence: 99%

In situ tritium recovery behavior from Li2TiO3 pebble bed under neutron pulse operation

Tsuchiya

Kikukawa

Hoshino

et al. 2004

Journal of Nuclear Materials

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Postirradiation examination of BEATRIX-II, phase I

Cited by 9 publications

References 7 publications

Ceramic breeder materials: Status and needs

Ceramic breeder materials: Status and needs

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li₂TiO₃Pebble Bed in Japan

In situ tritium recovery behavior from Li2TiO3 pebble bed under neutron pulse operation

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Postirradiation examination of BEATRIX-II, phase I

Cited by 9 publications

References 7 publications

Ceramic breeder materials: Status and needs

Ceramic breeder materials: Status and needs

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li2TiO3Pebble Bed in Japan

In situ tritium recovery behavior from Li2TiO3 pebble bed under neutron pulse operation

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In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li₂TiO₃Pebble Bed in Japan