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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
W. F. Naughton, M. J. Cenko, S. H. Levine, W. F. Witzig
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 256-272
Technical Paper | Fuel | doi.org/10.13182/NT74-A15918
Articles are hosted by Taylor and Francis Online.
A core management program has been effected for TRIGA reactors (TRICOM) which utilizes three basic types of information: (a) keff as a function of burnup, (b) relative changes in power fractions of fuel elements as a function of core burnup, and (c) reactivity worth curves for fissile isotopes and neutron absorbers. TRICOM has been programmed for an IBM system/360 using the FORTRAN IV language. Experimental measurements have been made with 8.5 wt% uranium and a mixture of 8.5 and 12 wt% uranium-fueled cores, and the results have been compared with those calculated by TRICOM. The analytical and experimental results compare favorably in all cases, particularly when some of the experimentally measured parameters are substituted for those derived theoretically. A significant result of this study program has been the development of an improved refueling scheme for The Pennsylvania State University’s Breazeale Nuclear Reactor which replaces depleted 8.5 wt% fuel with 12 wt% uranium fuel.
