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
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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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
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.
W. L. Pearl, E. G. Brush, G. G. Gaul, S. Leistikow
Nuclear Technology | Volume 3 | Number 7 | July 1967 | Pages 418-432
Technical Paper and Note | doi.org/10.13182/NT67-A27840
Articles are hosted by Taylor and Francis Online.
INCONEL alloy 625® fuel-cladding material has been corrosion-tested under heat-transfer conditions at metal temperatures up to 1500°F (816°C) in specially designed out-of-pile superheat facilities. The hydrogen and oxygen contents of the steam were controlled to simulate those found in boiling-water-reactor systems. The corrosion data from the 3600-h heat-transfer tests indicated good corrosion resistance up to the 1500°F metal temperature tested. A compositionally changed layer developed at the metal-oxide interface that appeared to reach a maximum depth at the higher temperatures. The heat-transfer test data indicated that except for a small buildup of oxide during the initial nonlinear transient corrosion period, most of the oxide formed in corrosion was carried downstream by the superheated steam. The uniform corrosion experienced by the INCONEL-625 when exposed isothermally to 1050 and 1150°F (566 and 621°C) for 10 000 h indicates an initially high-corrosion rate that decreases to a lower constant rate within the first 1000 h. A small proportion of the total oxide formed was gradually lost to the system.