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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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Gaston Kayser, Jean Charpenel, Claude Jamond
Nuclear Science and Engineering | Volume 128 | Number 2 | February 1998 | Pages 144-185
Technical Paper | doi.org/10.13182/NSE98-A1950
Articles are hosted by Taylor and Francis Online.
The SCARABEE-N in-pile tests were performed between 1983 and 1990. Their main objective was to study the consequences of a hypothetical total instantaneous blockage (TIB) at the entrance of a liquid-metal reactor subassembly at full power. After 14 tests, mainly with fresh fuel, this accident scenario may be fairly well described. It has been shown that no violent, energetic fuel/coolant interactions take place, that almost no fuel is ejected out of the fissile zone, and that the melt penetration into the neighboring subassemblies proceeds rapidly. Progress has been made on understanding the behavior of mixed boiling pools, and hexcan melt-through thresholds can be established.Codes have been developed (PHYSURA-GRAPPE and SURFASS), and SCARABEE-N tests have been used to help in the evaluation of others (SIMMER II and SABRE). Interesting information for other accident situations has been made available, especially for the transition phase.Concerning the specific case of the TIB accident, it has been shown that the evolution of the molten zone can be represented by calculations in which energy equations play the essential role. For a Superphénix-type subassembly, PHYSURA-GRAPPE and analytic calculations show that after ~30 s after the beginning of the blockage, there exists a serious risk of propagation beyond a 7-subassembly pool. This can be prevented only by an adequate detection system leading to scram before this time.The SCARABEE-N program helped to solve the problem for which it was designed; moreover, it yielded scientific expertise for other areas and was a precious training ground for many safety scientists and engineers. It also showed the limits of so-called mechanistic models for very complex problems and the sustained usefulness of simple engineering reasoning.