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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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OECD NEA meeting focuses on irradiation experiments
Members of the OECD Nuclear Energy Agency’s Second Framework for Irradiation Experiments (FIDES-II) joint undertaking gathered from September 29 to October 3 in Ketchum, Idaho, for the technical advisory group and governing board meetings hosted by Idaho National Laboratory. The FIDES-II Framework aims to ensure and foster competences in experimental nuclear fuel and structural materials in-reactor experiments through a diverse set of Joint Experimental Programs (JEEPs).
Adly B. Wahba, Fritz Steinhoff
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 1086-1096
Late Paper | TMI-2: Decontamination and Waste Management / Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A27699
Articles are hosted by Taylor and Francis Online.
The thermal-hydraulic code A THLET used to analyze the Three Mile Island Unit 2 accident was developed at the Gesellschaft für Reaktorsicherheit in the Federal Republic of Germany for safety analysis of pressurized water reactors with U-tube steam generators. First calculations of phase 1 of the accident without simulating the secondary sides were preliminary and have shown the need for accurate heat flow rates in the steam generators. The available values resulted in an incorrect system pressure behavior. Second calculations with detailed simulation of the once-through steam generator provided interesting information like the influence of flow resistance in the aspirator on cold-leg temperature and the dependence of system behavior on the rate and position of auxiliary feedwater injection.