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
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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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Latest News
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
Frank E. Motley, Richard P. Jenks
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 302-309
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27658
Articles are hosted by Taylor and Francis Online.
Work has been performed to develop a Three Mile Island Unit 2 (TMI-2) simulation model for MELPROG/TRAC capable of predicting the observed plant behavior that occurred during the accident of March 1979. A description of the TMI-2 plant model is presented, and calculation results through 174 min of the accident are discussed. Using the boundary conditions recommended for the TMI-2 Analysis Exercise, the calculation predicts pressurizer draining and core recovering prior to fuel rod damage. A parametric calculation (with reduced makeup flow) was also performed and is in better agreement with the observed plant behavior. Efforts are under way to proceed with an accurate simulation through phases 3 and 4 of the accident (174 to 227 min and 227 to 300 min, respectively).
