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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
NRC approves transfer of Vallecitos to North Star for D&D
By an order dated April 25, the Nuclear Regulatory Commission has approved the transfer of ownership of GE Hitachi Nuclear Energy’s Vallecitos Nuclear Center to NorthStar Group Services for nuclear decontamination, decommissioning, and environmental site restoration.
L. Ammirabile, A. Bieliauskas, A. Bujan, B. Toth, G. Gyenes, J. Dienstbier, L. Herranz, J. Fontanet, N. Reinke, A. Rizoiu, J. Jancovic
Nuclear Technology | Volume 172 | Number 2 | November 2010 | Pages 220-229
Technical Note | Reactor Safety | doi.org/10.13182/NT10-A10907
Articles are hosted by Taylor and Francis Online.
This paper presents an overview of the activities carried out in the framework of the SARNET project by the CIEMAT, INR, JRC/IE, GRS, UJV, and VUJE partners involved in the validation of ASTEC on fission product (FP) release and transport experiments simulating severe accident conditions in the reactor circuit and containment.These activities were mainly devoted to the analysis of the Phébus experiments, FPT0, FPT1, and FPT2, which provided fundamental reference data for the severe accident research. The ELSA, SOPHAEROS, CPA, and IODE modules were used for FP release from the bundle, transport in the circuit, containment thermal hydraulics and aerosol behavior, and iodine behavior in containment, respectively. Studies on aerosol behavior in the STORM experiments and iodine behavior in the ThAI experiments are also summarized.The paper describes not only the results of validation of some stand-alone or several coupled code modules but also the results of first integral calculations, when all the relevant modules of the ASTEC code were used to model the FP release and transport. In the integral calculations, no boundary conditions are to be defined by the code users for most of the code modules, but only at such interfaces were the boundary conditions applied in the experiment. The integral calculation allows more objective judgment about the combined uncertainties of the calculated results.Together with overview of the progress in the validation of the main ASTEC modules, this paper also points out what needs to be improved in the modeling of future ASTEC V2 code versions.