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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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!
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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?
Michael W. J. Lewis, Charles S. Campbell
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 460-469
Technical Paper | Materials | doi.org/10.13182/NT55-460
Articles are hosted by Taylor and Francis Online.
Steam generators for liquid-metal fast breeder reactors may be subject both to fretting wear as a result of flow-induced vibrations and to wear from larger amplitude sliding movements caused by thermal changes. Wear under these conditions is strongly adhesive so that in tests simulating the larger amplitude sliding of tubing through support plates, mechanical interaction of the wear scars results in high pseudo-friction forces for ferritic steels at the extremities of movement. With austenitic steel combinations in such tests, less wear is found but at temperatures above 500°C static adhesion after a period of dwell can give increased axial forces to initiate sliding, for example, up to three times the contact force at 560°C. A number of test mechanisms have been developed to evaluate the impact, impact-slide, and rubbing fretting behavior of these materials in sodium. With hemisphere-on-flat geometry, specific wear rates for austenitic steel combinations in impact-slide increase with temperature and decrease with time, while specific wear rates for ferritic steel combinations are approximately an order of magnitude greater (10−14 to 10−13 m3/Nm). In rubbing fretting, wear rates are broadly similar for austenitic and ferritic steel combinations. Specific wear rates decrease with slip amplitude and are of the order of 3 × 10−16 m3/Nm at 10 µm and 3 × 10−15 m3/Nm in excess of 100 µm.