Ultra-high tritium decontamination of simulated fusion fuel exhaust using a 2-stage palladium membrane reactor

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A 2-stage cold (non-tritium) PMR system was tested with the ITER mix in61 days of continuous operation. No decrease in performance was observed over the duration of the test. Decontamination factor (DF) was found to increase with decreasing inlet rate. Decontamination factors in excess of 1.4 {times} 10{sup 5} were obtained, but the exact value of the highest DF could not be determined because of analysis limitations. Results of the 61-day test were used to design a 2-stage PMR system for use in tritium testing. The PMR system was scaled up by a factor of 6 and built into a ... continued below

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8 p.

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Birdsell, S. A.; Willms, R. S. & Wilhelm, R. C. December 1996.

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Description

A 2-stage cold (non-tritium) PMR system was tested with the ITER mix in61 days of continuous operation. No decrease in performance was observed over the duration of the test. Decontamination factor (DF) was found to increase with decreasing inlet rate. Decontamination factors in excess of 1.4 {times} 10{sup 5} were obtained, but the exact value of the highest DF could not be determined because of analysis limitations. Results of the 61-day test were used to design a 2-stage PMR system for use in tritium testing. The PMR system was scaled up by a factor of 6 and built into a glovebox in the Tritium Systems Test Assembly (TSTA) of the Los Alamos National Laboratory. This system is approximately 1/5th of the expected full ITER scale. The ITER mix was injected into the PMR system for 31 hours, during which 4.5 g of tritium were processed. The 1st stage had DF = 200 and the 2nd stage had DF = 2.9 {times} 10{sup 6}. The overall DF = 5.8 {times} 10{sup 8}, which is greater than ITER requirements.

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8 p.

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INIS; OSTI as DE97000116

Source

  • ISFNT-4: 4th international symposium on fusion nuclear technology, Tokyo (Japan), 6-11 Apr 1997

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  • Other: DE97000116
  • Report No.: LA-UR--96-3212
  • Report No.: CONF-970404--1
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 459419
  • Archival Resource Key: ark:/67531/metadc676544

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  • December 1996

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  • July 25, 2015, 2:21 a.m.

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  • Dec. 4, 2015, 1:58 p.m.

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Birdsell, S. A.; Willms, R. S. & Wilhelm, R. C. Ultra-high tritium decontamination of simulated fusion fuel exhaust using a 2-stage palladium membrane reactor, article, December 1996; New Mexico. (digital.library.unt.edu/ark:/67531/metadc676544/: accessed August 16, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.