ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Discovering, Making, and Testing New Materials: SRNL’s Center For Hierarchical Waste Form Materials
Savannah River National Laboratory researchers are building on the laboratory’s legacy of using cutting-edge science to effectively immobilize nuclear waste in innovative ways. As part of the Center for Hierarchical Waste Form Materials, SRNL is leveraging its depth of experience in radiological waste management to explore new frontiers in the industry.
Fatma Yilmaz, Yassin A. Hassan, Douglas L. Porter, Oleg Romanenko
Nuclear Technology | Volume 144 | Number 3 | December 2003 | Pages 369-378
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT03-A3451
Articles are hosted by Taylor and Francis Online.
Material property data concerning the structural materials of EBR-II and BN350 have been compiled. The swelling formulations developed for Russian and American austenitic steels before reaching steady-state conditions are compared, and possible applications of the formulation for Russian steels to some compositionally similar American steels are discussed. The effects of slight composition and metallurgical condition differences on swelling can be used to explain the possible differences between the American steel data and the predictions for the corresponding Russian steel.Ultimate tensile strength and total elongation changes in Russian austenitic steels are correlated with swelling over a large swelling range (0 to 15%) and reveals total loss of ductility and strength as the amount of swelling reaches high values.Since austenitic steel is the main structural material of fast and light water reactors (LWRs) these findings can be applied to the LWR systems considering exposure temperature, dose rate, and neutron energy spectrum differences.