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
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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!
Latest Magazine Issues
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
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.
Imtiaz K. Madni, Xiao-Dong Guo
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 203-212
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34690
Articles are hosted by Taylor and Francis Online.
The MELCOR computer code has been used to simulate the National Research Universal full-length high-temperature 2 (FLHT-2) test. Input data for the analysis were obtained from the FLHT-2 test Data Report and from SCDAP input. Results are presented for the transient liquid level in the test bundle, heat transfer to the bypass flow, cladding and shroud temperatures, and hydrogen generation. Comparisons are made with experimental data and with SCDAP calculations. Several sensitivity calculations with MELCOR, which explore the impact of varying user-input modeling and time-step control parameters on the predicted behavior, were also carried out.
