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Preliminary assessment of corrosion product transport in fusion reactors

Author
Johnson, Jr, A. B.
Published
[Place of publication not identified] : [publisher not identified], 1973.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1973.
Physical Description
microfiche : negative ; 11 x 15 cm
Additional Creators
Vogelsang, W. F.

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Summary
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)
Report Numbers
BNWL-SA-4777; CONF-731101-48
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
NSA number: NSA-29-017424
OSTI Identifier 4378997
Research organization: Battelle Pacific Northwest Labs., Richland, Wash. (USA).
Research organization: Wisconsin Univ., Madison (USA). Dept. of Nuclear Engineering.
View MARC record | catkey: 42543667