ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
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.
Richard L. Moore, Daniel W. Golden, E. L. Tolman
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 990-1004
Late Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27691
Articles are hosted by Taylor and Francis Online.
A two-dimensional finite element model was developed to simulate the Three Mile Island Unit 2 core heatup between 174 and 224 min and the subsequent cooling of the consolidated core region after the relocation of ≃25 tonnes of core material to the lower plenum of the reactor at 224 min. The model considered heat losses at the surfaces of the degraded core zone, core material melting, convective heat transfer within the molten pool, and decay heat reduction from the release of the volatile fission products. The results obtained from the model indicate that at least 17% of the consolidated core material must have been molten at 174 min in order to generate the ≃25 tonnes of core material that relocated at 224 min. The cooldown calculation indicated that as long as the core remained covered with coolant, the core configuration would remain thermally stable with pool cooldown beginning at ∼324 min after the initiation of the accident.