Preliminary assessment of corrosion product transport in fusion reactors

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Corrosion which is tolerable from the standpoint of system mechanical integrity may cause substantial problems if the corrosion product is released and deposited at locations where it interferes with heat transfer or coolant flow. Furthermore, neutrons from the fusion reaction activate the corrosion product, causing radiation fields in maintenance areas near piping and components where the activated material deposits. Preliminary estimates suggest that formidable problems may occur in a lithium-cooled stainless steel primary circuit due to corrosion product deposition. If the estimated order of magnitude is confirmed in future studies, new concepts in corrosion control or corrosion product removal would ... continued below

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Pages: 11

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Johnson, A.B. Jr. & Vogelsang, W.F. November 1, 1973.

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Description

Corrosion which is tolerable from the standpoint of system mechanical integrity may cause substantial problems if the corrosion product is released and deposited at locations where it interferes with heat transfer or coolant flow. Furthermore, neutrons from the fusion reaction activate the corrosion product, causing radiation fields in maintenance areas near piping and components where the activated material deposits. Preliminary estimates suggest that formidable problems may occur in a lithium-cooled stainless steel primary circuit due to corrosion product deposition. If the estimated order of magnitude is confirmed in future studies, new concepts in corrosion control or corrosion product removal would need to be developed for lithium-cooled stainless steel CTR systems. Other fusion reactor system concepts and materials appear to offer alternatives which tend to minimize corrosion product transport. (auth)

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Pages: 11

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Dep. NTIS

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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.: BNWL-SA--4777
  • Report No.: CONF-731101--48
  • Grant Number: None
  • Office of Scientific & Technical Information Report Number: 4378997
  • Archival Resource Key: ark:/67531/metadc1025514

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Office of Scientific & Technical Information Technical Reports

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

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • November 1, 1973

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  • Oct. 15, 2017, 10:09 p.m.

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Johnson, A.B. Jr. & Vogelsang, W.F. Preliminary assessment of corrosion product transport in fusion reactors, article, November 1, 1973; Country unknown/Code not available. (digital.library.unt.edu/ark:/67531/metadc1025514/: accessed December 16, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.