Minimum activity blankets for commercial and experimental power reactors

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From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 1973). A new kind of tritium breeding blanket for fusion reactors is investigated. All components in the blanket are solid, including the lithium containing material, which eliminates problems of corrosion and materials compatibility. This permits the use of structural materials with very low neutron activation. A promising structural material is SAP, a pure aluminum strengthened by an Al/sub 2/O/sub 3/ dispersoid. Three types of blanket module designs are investigated in which the helium coolant exit temperature is substantially greater than the maximum operating temperature of ... continued below

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Pages: 25

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Powell, J.R.; Miles, F.T.; Aronson, A.; Winsche, W.E. & Bezler, P. January 1, 1973.

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From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 1973). A new kind of tritium breeding blanket for fusion reactors is investigated. All components in the blanket are solid, including the lithium containing material, which eliminates problems of corrosion and materials compatibility. This permits the use of structural materials with very low neutron activation. A promising structural material is SAP, a pure aluminum strengthened by an Al/sub 2/O/sub 3/ dispersoid. Three types of blanket module designs are investigated in which the helium coolant exit temperature is substantially greater than the maximum operating temperature of SAP ( approximates 400 deg C). Exit temperatures range from 500 deg C to above 1000 deg C, while breeding ratios range from 0.9 to 1.5, depending on design. Structural stress is approximates 2000 psi, which is approximates -20% of failure stress. The bred tritium diffuses from the lithium alloy or compound (e.g., LiAl), which has a much higher tritium pressure than pure lithium, into the helium coolant stream from which it is recovered. Depending on processing rates, temperature, LiAl inventory, and the amount of scavenging by added H/sub 2/ , the tritium blanket inventory ranges from approximates 10/sup 5/ to 10/sup 6/ curies. Short lived activities, principall y /sup 24/Na (15 hour half life), decay to a negligible amount in a few days, leaving a long lived inventory of approximates 10/sup 4/ curies/100O MW(e) (principally /sup 26/Al (7.3 x 10/sup 5/ year half life)!. This material appears to present no problems of permanent waste disposal. Because of the very low inventory of long lived activities, blanket repair or replacement seems relatively simple. (auth)

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Pages: 25

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Dep. NTIS

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  • 5. symposium on engineering problems of fusion research, Princeton, New Jersey, USA, 6 Nov 1973

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  • Report No.: BNL--18439
  • Report No.: CONF-731114--50
  • Grant Number: None
  • Office of Scientific & Technical Information Report Number: 4344794
  • Archival Resource Key: ark:/67531/metadc1023440

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  • January 1, 1973

Added to The UNT Digital Library

  • Oct. 15, 2017, 10:09 p.m.

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  • Oct. 26, 2017, 12:52 p.m.

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Powell, J.R.; Miles, F.T.; Aronson, A.; Winsche, W.E. & Bezler, P. Minimum activity blankets for commercial and experimental power reactors, article, January 1, 1973; Upton, New York. (digital.library.unt.edu/ark:/67531/metadc1023440/: accessed October 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.