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Division Spotlight
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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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.
