ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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!
Latest Magazine Issues
Apr 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
May 2024
Fusion Science and Technology
Latest News
Fuel supply chain updates as U.S. and allies “sever dependency” on Russian U
The United States has an ambitious goal: to establish a high-assay low enriched-uranium advanced nuclear fuel supply chain, revive the once thriving nuclear fuel market for low-enriched uranium in the nation, and “reestablish U.S. leadership in nuclear energy more broadly.” Making a success of that could have impacts beyond the nuclear sector. According to the Department of Energy’s Office of Nuclear Energy, “Expanding domestic LEU and HALEU enrichment production will be essential for fueling the clean energy required to bring down emissions in all sectors of the economy—including in hard-to-abate sectors such as manufacturing and industrial—while delivering high paying jobs to communities across the country.”
D. Pun-Quach, P. Sermer, F. M. Hoppe, O. Nainer, B. Phan
Nuclear Technology | Volume 181 | Number 1 | January 2013 | Pages 170-183
Technical Paper | Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Reactor Safety | doi.org/10.13182/NT13-A15765
Articles are hosted by Taylor and Francis Online.
This paper presents a best estimate plus uncertainty (BEPU) methodology applied to dryout, or critical channel power (CCP), modeling based on a Monte Carlo approach. This method involves the identification of the sources of uncertainty and the development of error models for the characterization and separation of epistemic and aleatory uncertainties associated with the CCP parameter. Furthermore, the proposed method facilitates the use of actual operational data leading to improvements over traditional methods, such as sensitivity analysis, which assume parametric models that may not accurately capture the possible complex statistical structures in the system input and responses.