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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
X-energy, Dow apply to build an advanced reactor project in Texas
Dow and X-energy announced today that they have submitted a construction permit application to the Nuclear Regulatory Commission for a proposed advanced nuclear project in Seadrift, Texas. The project could begin construction later this decade, but only if Dow confirms “the ability to deliver the project while achieving its financial return targets.”
F. Nagase, R. O. Gauntt, M. Naito
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 499-510
Technical Paper | doi.org/10.13182/NT16-10
Articles are hosted by Taylor and Francis Online.
The Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF) project, run by the Organisation for Economic Co-operation and Development/Nuclear Energy Agency, was established in November 2012. The primary objectives of this benchmark study are to estimate accident progression and status inside the nuclear reactors, including the distribution of fuel debris, and consequently, to contribute to the decommissioning activity at the Fukushima Daiichi nuclear power plant. Altogether, 17 organizations from eight countries calculated the thermohydraulic behavior inside the three reactors for the time span of about 6 days from the occurrence of the earthquake with their severe accident integral codes. Since many boundary conditions are unknown for the accident, those necessary for the calculation were discussed and determined by the participants.
The results submitted were compared on coolant level change, hydrogen generation, initiation and progression of melt in fuel bundle and control blade, failure of reactor pressure vessel, distribution and composition of molten and solidified materials, and progression of the molten core–concrete interaction. Finally, the current estimates of the accident progression and status inside the reactors were summarized together with the still remaining uncertainties and data needs as the output from the project.