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!
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Nuclear Science and Engineering
May 2025
Nuclear Technology
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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.
Bernard R. Bandini, Anthony J. Baratta, Victor R. Fricke
Nuclear Technology | Volume 81 | Number 3 | June 1988 | Pages 370-380
Technical Paper | Nuclear Safety | doi.org/10.13182/NT88-A16058
Articles are hosted by Taylor and Francis Online.
Since the March 1979 accident, the source range monitors (SRMs) at Three Mile Island Unit 2 (TMI-2) have been reading several orders of magnitude higher than would be expected in a normal shutdown core. A study in which these anomalous SRM readings are analyzed and the cause determined is reported. Here, the DOT 4.3 two-dimensional transport code was used to simulate the SRM response and the response of an axial string of solid-state track recorders by modeling the neutronics of the damaged TMI-2 core. This modeling has indicated the presence of ∼10 tonnes of fuel material in the lower vessel plenum, a condition that was subsequently verified by direct observation. The computational model, the method of cross-section preparation, and an analysis of the various core neutron sources are described, as well as the results obtained from this effort.