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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
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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ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
G. J. Theus
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 388-397
Technical Paper | Reactor | doi.org/10.13182/NT76-A31521
Articles are hosted by Taylor and Francis Online.
High-temperature electrochemical tests have resulted in the stress corrosion cracking of Inconel-600 and Incoloy-800 (registered trademarks, International Nickel Company), and Type 304 stainless steel in caustic solutions. Results show that stress corrosion cracking of these alloys can be prevented or accelerated by varying their electrochemical potential. To a certain extent, the same effect can be achieved by altering the gas atmosphere above the test solution from a pure nitrogen cover gas to a mixture of 5% H2 and 95% N2. The effect of the cover gas can then be negated by adjusting the specimen’s electrochemical potential either to cause or to inhibit stress corrosion cracking. These types of experiments lead to a better determination of the boundary conditions within which stress corrosion cracking of the alloys occurs. Some specifics of the test results reveal that in deoxygenated caustic solutions, Inconel-600 cracks intergranularly at mildly anodic potentials; Incoloy-800 cracks transgranularly at reduced potentials (at or near the open circuit potential) and intergranularly at highly oxidizing potentials; and cracking is mixed (transgranular/intergranu-lar) for Type 304 stainless steel at or near the open circuit potential. The severity of cracking for both Inconel-600 and Incoloy-800 in deoxygenated caustic solutions is reduced by giving the materials a simulated post-weld heat treatment (1150°F for 18 h). Test results on Inconel-600 show that high-carbon (0.06%) material cracks less severely than low-carbon (0.02%) material, in both the simulated post-weld heat-treated condition and the mill-annealed condition. The results we obtained with the electrochemical corrosion techniques agree with results obtained using conventional corrosion methods for caustic stress corrosion cracking. Moreover, many metallurgical variables, which promote or retard caustic cracking, are the same as those conditions that promote or retard high-temperature high-purity water failures—particularly in the case of Inconel-600.