Calculations on the compatibility of refractory metals in a tritium environment and cold trapping method for tritium removal from a lithium blanket

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From joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Energy Exhibition; San Francisco, California, USA (11 Nov 1973). Thermodynamic calculations were made on the distribution of hydrogen and tritium between various refractory metals and liquid lithium as a function of temperature. The limiting tritium pressures that can be attained by cold trapping of secondary liquid metals such as Na, K, and NaK were calculated. In the absence of tritium breeding, these pressures are 2.5 x 10/sup -5/, 2 x 10/ sup -7/ and 1.2 x 10/sup -10/o torr for Na, K, and NaK, respectively, ... continued below

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Pages: 40

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Natesan, K. & Smith, D.L. January 1, 1973.

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From joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Energy Exhibition; San Francisco, California, USA (11 Nov 1973). Thermodynamic calculations were made on the distribution of hydrogen and tritium between various refractory metals and liquid lithium as a function of temperature. The limiting tritium pressures that can be attained by cold trapping of secondary liquid metals such as Na, K, and NaK were calculated. In the absence of tritium breeding, these pressures are 2.5 x 10/sup -5/, 2 x 10/ sup -7/ and 1.2 x 10/sup -10/o torr for Na, K, and NaK, respectively, and these correspond to tritium concentrations in lithium of 45, 4, and <1 ppM, respectively, at 700 deg C. For a thermonuclear reactor of 1000 MW(t) thermal power with a tritium breeding rate of 150 g/day, a tritium recovery system that incorporates a separate lithium purification loop with niobium as the permeable membrane, NaK as the secondary heat transport fluid and with tungsten cladding on the IHX tubes seems to yield tritium pressures of ~10/sup -9/ torr or less in the secondary system. This leads to tritium release rate of ~10/sup -6/g/ hr to the steam system for a steam generator clad with tungsten and operating at ~600 deg C. This corresponds to activity release rate of~300 Ci/yr. (17 figures, 61 references) (auth)

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Pages: 40

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  • Joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Energy Exhibition, San Francisco, California, USA, 11 Nov 1973

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  • Report No.: CONF-731101--37
  • Grant Number: None
  • Office of Scientific & Technical Information Report Number: 4381872
  • Archival Resource Key: ark:/67531/metadc1022371

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Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • January 1, 1973

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  • Oct. 15, 2017, 10:09 p.m.

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  • Oct. 27, 2017, 3:33 p.m.

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Natesan, K. & Smith, D.L. Calculations on the compatibility of refractory metals in a tritium environment and cold trapping method for tritium removal from a lithium blanket, article, January 1, 1973; Illinois. (digital.library.unt.edu/ark:/67531/metadc1022371/: accessed September 25, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.