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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
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.
