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.
Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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!
Latest Magazine Issues
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
NEI chief executive highlights “unlimited potential” for nuclear in state of the industry address
Korsnick
In the Nuclear Energy Institute’s annual State of the Nuclear Energy Industry report, NEI president and CEO and Maria Korsnick expressed optimism about the nuclear industry and she issued a call to action.
Her address was part of NEI’s Nuclear Energy Policy forum. The forum, being held in Washington, D.C., on May 20 and May 21, brings together industry leaders, policy stakeholders, and clean energy experts to discuss nuclear advocacy. Korsnick’s remarks focused on the private capital flowing into the industry, progress on regulatory reform and new nuclear technology, and how the U.S. is trying to take the lead on the global nuclear stage.
“We are here at an unprecedented time in our industry history,” Korsnick said. “I’m proud to say that the nuclear industry has a future of unlimited potential.”
Masami Yajima, Naoaki Takashima, Sadaaki Sasaki, Satsuharu Takimoto
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 120-127
Technical Paper | Material | doi.org/10.13182/NT82-A32887
Articles are hosted by Taylor and Francis Online.
Stress corrosion cracking (SCC) of austenitic materials has been investigated under high temperature water into which a trace level of chemical reagent for reactor process decontamination was injected to simulate residual chemical reagent in normal reactor cooling water. Creviced bend beam and 4-in. pipe tests have been performed with two kinds of concentrated-type reagents and two kinds of dilute-type reagents. It was found that concentrated-type reagents, when injected into high temperature water by 1/1000 of a specified concentration, work as an oxygen scavenger and significantly inhibit intergranular stress corrosion cracking in both sensitized Type 304 stainless steel and Inconel alloys 600 and X-750. Dilute-type reagents did not reduce dissolved oxygen (DO) at all and one of the reagents tested accelerated SCC in Type 304 stainless steel when injected into high temperature water by 1/1000 of a specified concentration. Another dilute-type reagent partially suppressed cracking of Type 304 stainless steel at the same residual reagent concentration. It is suggested that residual level decontamination reagent will work in two ways, depending on residual concentration. When residual concentration is rather high, it will work as an oxygen scavenger and will not have detrimental effects in terms of SCC; when reagent concentration is very diluted, it will accelerate cracking in heavily sensitized Type 304 stainless steel, regardless of the type or kind of decontamination reagent. This effect will be reduced in actual operation since the DO level is ∼0.2 ppm maximum in the normal reactor water.
