ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
April 2026
Latest News
ANS, UCOR sign MOU for workforce development program
The American Nuclear Society and United Cleanup Oak Ridge have signed a memorandum of understanding that establishes a framework for collaboration to advance ANS workforce training and certification programs serving the nuclear industry.
According to the document, UCOR will provide “operational insights and subject matter expertise to inform ANS’s professional development and credentialing offerings, including the Certified Nuclear Professional [CNP] program.” The collaboration will strengthen UCOR’s workforce development efforts while advancing ANS’s mission to sustain and expand the national nuclear workforce pipeline and capabilities.
J. H. DeVan, J. C. Griess
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 398-405
Technical Paper | Reactor | doi.org/10.13182/NT76-A31522
Articles are hosted by Taylor and Francis Online.
We have studied the general corrosion of 2¼ Cr— 1 Mo steel in pure superheated steam, in impure superheated and saturated steam, and under nucleate boiling conditions. The test parameters were selected to provide information relevant to the use of this steel for the Clinch River Breeder Reactor superheaters and evaporators. The oxidation rate of 2¼ Cr—1 Mo steel in superheated steam was measured under heat transfer conditions at 510 to 540°C (950 to 1005°F), and was times that measured under iso thermal conditions. Extensive general attack of stressed 2¼ Cr—1 Mo steel specimens occurred in cyclic tests in superheated and saturated steam with chloride and oxygen additions, although no cracking or localized attack was observed. Considerably less attack occurred under superheat conditions or in the absence of oxygen. Tests under nucleate boiling conditions were operated to evaluate crevice effects associated with porous films on heat transfer surfaces. Significant crevice corrosion was produced in water containing 10 ppm chloride; a heavier but more general attack occurred in treated cooling tower water.