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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jul 2024
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Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Lee A. James
Nuclear Technology | Volume 74 | Number 1 | July 1986 | Pages 84-92
Technical Paper | Material | doi.org/10.13182/NT86-A33821
Articles are hosted by Taylor and Francis Online.
Fatigue-crack growth specimens from a number of austenitic stainless steels and weldments [annealed Types 304 and 316, 20% cold-worked Type 316, SA-351 Grade CF8, Type 304/308 shielded-metal-arc (SMA) weldments, and Type 316/IN-82/IN-718 gastungsten-arc weldments] were irradiated in Experimental Breeder Reactor-II. Postirradiation crack-growth testing showed little or no effect of irradiation on the crack growth behavior of annealed Type 304, coldworked Type 316, and Type 304/308 SMA weldments. On the other hand, irradiation produced a minor reduction in crack growth rates in annealed Type 316 and minor increases in crack growth rates in SA-351 Grade CF8 castings and Type 316/IN-82/IN-718 GTA weldments over certain ranges of ΔK.
