BEATRIX-II, phase II: Data summary report

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The BEATRIX-II 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 II activities, which included two in situ tritium-recovery canisters: temperature-change and temperature-gradient. The temperature-change canister contained a Li{sub 2}O ring specimen that had a nearly uniform temperature profile and was capable of temperature changes between 530 and 640{degrees}C. The temperature-gradient canister contained a Li{sub 2}ZrO{sub 3} pebble bed operating under a thermal gradient of 440 to 1100{degrees}C. Postirradiation examination ... continued below

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132 p.

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Slagle, O. D. & Hollenberg, G. W. May 1996.

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  • Pacific Northwest Laboratory
    Publisher Info: Pacific Northwest Lab., Richland, WA (United States)
    Place of Publication: Richland, Washington

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Description

The BEATRIX-II 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 II activities, which included two in situ tritium-recovery canisters: temperature-change and temperature-gradient. The temperature-change canister contained a Li{sub 2}O ring specimen that had a nearly uniform temperature profile and was capable of temperature changes between 530 and 640{degrees}C. The temperature-gradient canister contained a Li{sub 2}ZrO{sub 3} pebble bed operating under a thermal gradient of 440 to 1100{degrees}C. Postirradiation examination was carried out to characterize the Phase II 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-II, Phase II, irradiation experiment provided an extensive data base on the in situ tritium-release characteristics of Li{sub 2}O and Li{sub 2}ZrO{sub 3} 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 Li{sub 2}O and Li{sub 2}ZrO{sub 3}. Tritium inventories measured confirmed that Li{sub 2}O and Li{sub 2}ZrO{sub 3} exhibited very low tritium retention during the Phase II irradiation. Tritium inventories in Li{sub 2}ZrO{sub 3} after Phase II tended to be larger than those found for Li{sub 2}ZrO{sub 3} 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 ceramics and beryllium under conditions similar to a fusion blanket. It is concluded that Li{sub 2}O and Li{sub 2}ZrO{sub 3} should remain leading candidates for use in a solid-breeder fusion-blanket application.

Physical Description

132 p.

Notes

OSTI as DE96011596

Source

  • Other Information: PBD: May 1996

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  • Other: DE96011596
  • Report No.: PNNL--11148
  • Grant Number: AC06-76RL01830
  • DOI: 10.2172/245644 | External Link
  • Office of Scientific & Technical Information Report Number: 245644
  • Archival Resource Key: ark:/67531/metadc664776

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  • May 1996

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

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  • April 7, 2016, 2:25 p.m.

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Slagle, O. D. & Hollenberg, G. W. BEATRIX-II, phase II: Data summary report, report, May 1996; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc664776/: accessed October 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.