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Title: BEATRIX-II: In situ tritium recovery from Li[sub 2]O and Li[sub 2]ZrO[sub 3] irradiated in a fast neutron flux

Abstract

The BEATRIX-II irradiation experiment was an in situ, fast neutron, tritium release experiment to evaluate the performance of ceramic fusion solid breeders at extended burnups. The experiment consisted of two sequential irradiations: Phase I for 300 EFPD and Phase II for 200 EFPD that resulted in lithium burnups from 4[endash]6%. Thin-walled Li[sub 2]O ring specimens capable of temperature changes were irradiated in both Phase I and Phase II. Temperature changes were also used to determine the tritium inventory and to characterize the effect or irradiation history and sweep gas composition. Solid-cylindrical temperature-gradient specimens were irradiated to characterize their stability with respect to heat transport, lithium transport and physical integrity over the duration of the experiment. Phase I included a solid monolithic specimen of Li[sub 2]O while Phase II included a sphere bed of Li[sub 2]ZrO[sub 3].

Authors:
;  [1];  [2];  [3]
  1. Pacific Northwest Lab., Richland, WA (United States)
  2. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of Fuels and Materials Research
  3. Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Labs.
Publication Date:
Research Org.:
Pacific Northwest Lab., Richland, WA (United States)
Sponsoring Org.:
USDOE; USDOE, Washington, DC (United States)
OSTI Identifier:
7173710
Report Number(s):
PNL-SA-20872; CONF-920930-12
ON: DE93001560; TRN: 92-038328
DOE Contract Number:  
AC06-76RL01830
Resource Type:
Conference
Resource Relation:
Conference: 17. symposium on fusion technology, Rome (Italy), 14-18 Sep 1992
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Fu; Ma; BREEDING BLANKETS; PERFORMANCE TESTING; LITHIUM OXIDES; TRITIUM RECOVERY; THERMONUCLEAR REACTOR MATERIALS; PHYSICAL RADIATION EFFECTS; CERAMICS; IRRADIATION; NEUTRON FLUX; TEMPERATURE DEPENDENCE; TEMPERATURE GRADIENTS; ZIRCONIUM OXIDES; ALKALI METAL COMPOUNDS; CHALCOGENIDES; LITHIUM COMPOUNDS; MATERIALS; OXIDES; OXYGEN COMPOUNDS; RADIATION EFFECTS; RADIATION FLUX; REACTOR COMPONENTS; TESTING; TRANSITION ELEMENT COMPOUNDS; ZIRCONIUM COMPOUNDS; 700450* - Fusion Technology- Blankets & Cooling Systems- (1992-); 700460 - Fusion Technology- Heating & Fueling Systems; Fuels- (1992); 700480 - Fusion Technology- Component Development; Materials Studies- (1992-)

Citation Formats

Slagle, O D, Hollenberg, G W, Kurasawa, T, and Verrall, R A. BEATRIX-II: In situ tritium recovery from Li[sub 2]O and Li[sub 2]ZrO[sub 3] irradiated in a fast neutron flux. United States: N. p., 1992. Web.
Slagle, O D, Hollenberg, G W, Kurasawa, T, & Verrall, R A. BEATRIX-II: In situ tritium recovery from Li[sub 2]O and Li[sub 2]ZrO[sub 3] irradiated in a fast neutron flux. United States.
Slagle, O D, Hollenberg, G W, Kurasawa, T, and Verrall, R A. 1992. "BEATRIX-II: In situ tritium recovery from Li[sub 2]O and Li[sub 2]ZrO[sub 3] irradiated in a fast neutron flux". United States. https://www.osti.gov/servlets/purl/7173710.
@article{osti_7173710,
title = {BEATRIX-II: In situ tritium recovery from Li[sub 2]O and Li[sub 2]ZrO[sub 3] irradiated in a fast neutron flux},
author = {Slagle, O D and Hollenberg, G W and Kurasawa, T and Verrall, R A},
abstractNote = {The BEATRIX-II irradiation experiment was an in situ, fast neutron, tritium release experiment to evaluate the performance of ceramic fusion solid breeders at extended burnups. The experiment consisted of two sequential irradiations: Phase I for 300 EFPD and Phase II for 200 EFPD that resulted in lithium burnups from 4[endash]6%. Thin-walled Li[sub 2]O ring specimens capable of temperature changes were irradiated in both Phase I and Phase II. Temperature changes were also used to determine the tritium inventory and to characterize the effect or irradiation history and sweep gas composition. Solid-cylindrical temperature-gradient specimens were irradiated to characterize their stability with respect to heat transport, lithium transport and physical integrity over the duration of the experiment. Phase I included a solid monolithic specimen of Li[sub 2]O while Phase II included a sphere bed of Li[sub 2]ZrO[sub 3].},
doi = {},
url = {https://www.osti.gov/biblio/7173710}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Sep 01 00:00:00 EDT 1992},
month = {Tue Sep 01 00:00:00 EDT 1992}
}

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