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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
W. D. Fletcher, D. D. Malinowski
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 356-373
Technical Paper | Reactor | doi.org/10.13182/NT76-A31518
Articles are hosted by Taylor and Francis Online.
Service exposure has been accrued in 66 steam generators tubed with Inconel-600. Localized corrosion coincident with sludge deposition in low flow-velocity zones has been observed. Inter granular cracking has been attributed to stress-assisted caustic corrosion resulting from hydrolysis of condenser inleakage contaminants or sodium phosphate reactions with feedwater corrosion products. Wall thinning or wastage is attributed to the formation of high-concentration sodium phosphate solutions under the sludge blanket. The resistance of Inconel-600 to these corrosion mechanisms is comparable or superior to that of other candidate tube materials. The experience gathered points strongly to environmental and thermal/hydraulic factors rather than materials considerations as the predominant influence on the occurrence of localized corrosion. Mechanical modifications designed to reduce the number of tubes in zones of low flow-velocity are being installed into operating units; current production units have incorporated design features including a flow distribution baffle to improve the thermal/ hydraulic conditions over prior models. Rigorous control of feedwater impurities is being applied to reduce the probability of creating a corrosive environment in the steam generators.