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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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?
P. E. Gethard, L. R. Zumwalt
Nuclear Technology | Volume 3 | Number 11 | November 1967 | Pages 679-685
Technical Paper and Note | doi.org/10.13182/NT67-A27903
Articles are hosted by Taylor and Francis Online.
The diffusion of strontium and cesium through thin layers (100 μm) of isotropic pyrolytic carbon has been measured over the temperature range 1000 to 1700°C. Diffusion coefficients observed for cesium are orders of magnitude lower than those for strontium. The diffusion rates for both series are much lower than those observed in porous poly crystalline graphite, where little difference is seen between cesium and strontium. When constant chemical potential sources are used, chemical- and self-diffusion measurements for strontium give identical results in the Sr concentration range 0.01 to 0.2 wt%. There is apparently no concentration effect for cesium over the range 1.0 × 10−5 to 0.15 wt%. The difference between strontium and cesium diffusion in pyrolytic carbon is attributed to the greater steric effect of the pyrolytic-carbon defect structure relative to cesium.