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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Digital control system installed at China’s Linglong One
Earlier this month, the first digital control system was put in place at Linglong One, a small modular reactor demonstration project being built at the Changjiang nuclear power plant in Hainan Province. This is the world’s first land-based commercial SMR and is controlled by China National Nuclear Power Co. Ltd., a subsidiary of the China National Nuclear Corporation (CNNC).
A. Bujan, B. Tóth, A. Bieliauskas, R. Zeyen, C. Housiadas
Nuclear Technology | Volume 169 | Number 1 | January 2010 | Pages 1-17
Technical Paper | Reactor Safety | doi.org/10.13182/NT10-A9339
Articles are hosted by Taylor and Francis Online.
Phébus FP tests study the phenomenology of severe accidents in water-cooled nuclear reactors. The first test, FPT0, was performed with fuel irradiated for only 1 week; the second test, FPT1, was performed with fairly similar boundary conditions but with irradiated fuel (burnup: 23 GWd/t). The objective of this work is, on the one hand, to summarize the main experimental results of these two tests concerning the behavior and transport of fission products and structural materials in the circuit and, on the other hand, to identify or to confirm any modeling weaknesses in the SOPHAEROS/ASTEC V1 module used for interpreting the experimental results. Besides comparison with available experimental data, the main results of the entire circuit analyses are compared with former SOPHAEROS/ASTEC V0 analyses and, for so-called quasi-separated steam generator tubes, with one- and two-dimensional Eulerian and Lagrangian (particle tracking) models.Concerning the transport of iodine vapor species, it is shown that the results obtained are compatible with passage of nonnegligible amounts of the measured highly volatile iodine through circuit to containment. It is also shown that these results depend heavily on the considered kinetics of Cd release from the bundle.