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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
Werner Schenk, Heinz Nabielek
Nuclear Technology | Volume 96 | Number 3 | December 1991 | Pages 323-336
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-3-323
Articles are hosted by Taylor and Francis Online.
The essential feature of small, modular high-temperature reactors (HTRs) is the inherent limitation in maximum accident temperature to below 1600°C combined with the ability of coated particle fuel to retain all safety-relevant fission products under these conditions. To demonstrate this ability, spherical fuel elements with modern TRISO particles are irradiated and subjected to heating tests. Even after extended heating times at 1600°C, fission product release does not exceed the already low values projected for normal operating conditions. Details of fission product distribution within spherical fuel elements heated at constant temperatures of 1600, 1700, and 1800°C are presented. The measurements confirm the silicon carbide (SiC) coating layer as the most important fission product barrier up to 1800° C. If the SiC fails (or is defective), the following transport properties at 1600 to 1800°C can be observed: cesium shows the fastest release from the UO2 kernel but is highly sorbed in the buffer layer of the particle and in the matrix graphite of the sphere; strontium is retained strongly both in UO2 kernels and in matrix graphite, but can penetrate SiC in some cases where cesium is still completely retained; only if all coating layers are breached can iodine and noble gases be released. For the first 100 h at 1600°C (enveloping all possible accident scenarios of small HTRs), these fission products are almost completely retained in the coated particles.